RU2536181C2 - Fuel assembly of fission nuclear reactor, which has possibility of controlled removal of volatile products of nuclear fission and heat released by combustion wave in fission nuclear reactor on running wave - Google Patents

Abstract

FIELD: power industry.

SUBSTANCE: fuel assembly of a fission nuclear reactor has a possibility of controlled removal of volatile products of nuclear fission and heat released by a combustion wave in a nuclear reactor. A fuel assembly includes a casing that can contain porous mass of nuclear fuel with a nuclear fission volatile product. A fluid medium control subassembly is connected to the casing and can control a removal process of at least some part of nuclear fission volatile products from porous mass of nuclear fuel. Besides, the fluid medium control subassembly has a possibility of circulation of the fluid medium releasing the heat through porous mass of nuclear fuel for removal of the heat produced by nuclear fuel mass.

EFFECT: providing deep burnout of fuel and sustained campaign.

36 cl, 213 dwg

Description

BACKGROUND OF THE INVENTION

This invention generally relates to fuel assemblies of a nuclear reactor and, more particularly, relates to a fuel assembly of a nuclear fission reactor and a system configured to control the removal of volatile nuclear fission products and heat generated by a combustion wave in a traveling wave fission reactor, and related with them a way.

It is known that in an existing nuclear fission reactor, neutrons of known energy are captured by nuclides having a high atomic mass. The resulting composite nucleus is divided into nuclear fission products, which include two fragments of nuclear fission with a lower atomic mass, as well as decay products. Known nuclides that undergo such nuclear fission under the influence of neutrons of all energies include Uranus-233, Uranus-235 and Plutonium-239, which are fissile nuclides. For example, thermal neutrons with a kinetic energy of 0.0253 eV (electron volts) can be used to fission Uranium-235 nuclei. The fission of Thorium-232 and Uranium-238, which are reproducing nuclides, will not undergo forced fission, except in the case of fast neutrons, which have a kinetic energy of at least 1 MeV (million electron volts). The total kinetic energy released in each fission event is about 200 MeV. This kinetic energy ultimately turns into heat.

Moreover, the nuclear fission process, which begins with the original neutron source, releases additional neutrons and also converts kinetic energy into heat. This leads to a self-sustaining chain reaction, which is accompanied by continued heat generation. For each neutron absorbed, more than one neutron is released until the nucleus subject to nuclear fission is depleted. This phenomenon is used in commercial nuclear reactors for the continuous production of heat, which, in turn, is used to generate electricity.

Attempts have been made to solve the problem of the accumulation of nuclear fission products during reactor operation. US patent No. 4285891, issued August 25, 1981 to Lane A. Bray et al, entitled “Method for Removing Gaseous Fission Products from Irradiated Fuel,” discloses a method for removing volatile nuclear fission products from irradiated fuel by first passing hydrogen-containing inert gas through a fuel that heated to a high temperature, at least 1000 degrees Celsius, and then pure inert gas is passed through the fuel, which is at an elevated temperature.

Another approach is disclosed in US patent No. 5268947, issued December 7, 1993 in the name of Bernard Bastide et al. Entitled "Nuclear fuel elements containing a trap for oxide-based nuclear fission products." This patent discloses a nuclear fuel element containing sintered granules, which is surrounded by a metal shell and allows the capture of nuclear fission products, characterized in that the granules contain or are coated with a means for capturing nuclear fission products, or the shell inside is coated with a means for capturing nuclear fission products. Nuclear fission products are captured in a trap, forming oxygen-containing compounds with a capture agent that are stable at high temperature.

SUMMARY OF THE INVENTION

According to an embodiment of the present invention, there is provided a fuel assembly of a nuclear fission reactor configured to control the removal of volatile nuclear fission products released by a combustion wave in a traveling wave nuclear fission reactor, comprising a casing configured to receive a porous mass of nuclear fuel, and a control subassembly a fluid connected to the casing and configured to control the removal of at least a portion of the volatile fission products and s porous mass of nuclear fuel.

According to an embodiment of the present invention, there is provided a fuel assembly of a nuclear fission reactor configured to control the removal of volatile nuclear fission products released by a combustion wave in a fuel assembly of a nuclear fission reactor, comprising a casing configured to receive a heat generating mass of nuclear fuel that limits a large the number of pores containing volatile fission products and a fluid control subassembly connected to the casing and configured to control the removal of at least a portion of volatile fission products from nuclear fuel pore weight control remove at least a portion of heat generated by the nuclear fuel mass.

In accordance with an embodiment of the present invention, there is provided a system for the controlled removal of volatile fission products released in the presence of a combustion wave in a fuel assembly of a nuclear fission reactor, comprising a casing configured to receive a porous mass of nuclear fuel that limits a large number of pores containing volatile nuclear products division, and a fluid control subassembly connected to the casing and designed to control the removal of at least a portion of the fly their nuclear fission products from the porous mass of nuclear fuel.

According to an embodiment of the present invention, there is provided a system for the controlled removal of volatile nuclear fission products released in the presence of a combustion wave in a fuel assembly of a nuclear fission reactor, comprising a casing configured to receive a heat generating mass of nuclear fuel that limits a large number of interconnected pores with open cells containing volatile fission products, and a fluid control subassembly connected to the casing and intended minutes to control the removal of at least part of volatile fission products from the nuclear pore and fuel mass for controlled removal of at least part of the heat generated by the nuclear fuel mass.

In accordance with an embodiment of the present invention, there is provided a method for assembling a fuel assembly of a nuclear fission reactor configured to control the removal of volatile nuclear fission products released by a combustion wave in a traveling wave fission reactor, comprising using a casing containing a porous mass of nuclear fuel and attaching a unit control fluid to the casing to control the removal of at least part of the volatile fission products from the porous mass of nuclear The fuel in a large number of locations corresponding to the combustion wave nuclear reactor divided by the traveling wave, by controlling the fluid flow in multiple areas fission reactor traveling wave near a large number of locations corresponding to the combustion wave.

In accordance with an embodiment of the present invention, there is provided a method for assembling a fuel assembly of a nuclear fission reactor configured to control the removal of volatile nuclear fission products released by a combustion wave in a traveling wave nuclear fission reactor, comprising using a casing containing a heat generating mass of nuclear fuel that limits a large the number of interconnected pores with open cells, and the connection of the fluid control unit to the casing for control the removal of at least a portion of the volatile fission products from the pores of the mass of nuclear fuel and to control the removal of at least a portion of the heat released by the mass of nuclear fuel at those locations that correspond to the combustion wave of the nuclear fission reactor on a traveling wave, by controlling the flow of fluid in those areas of the nuclear fission reactor on a traveling wave, which are near the locations corresponding to the combustion wave.

According to an embodiment of the present invention, there is provided a method comprising controlling the removal of volatile nuclear fission products at a large number of locations corresponding to a burning wave of a nuclear fission reactor on a traveling wave, and controlling the flow of fluid in a large number of regions of a nuclear fission reactor near a large number of locations, corresponding to the combustion wave.

In accordance with an embodiment of the present invention, there is provided a method of operating a fuel assembly of a nuclear fission reactor configured to control the removal of volatile fission products released by a combustion wave in a traveling wave fission reactor, comprising using a casing containing a porous mass of nuclear fuel containing volatile products nuclear fission, and the use of a fluid control assembly coupled to the casing and designed to control removal at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to a combustion wave in a traveling fission nuclear reactor by controlling fluid flow in a large number of regions of a traveling wave fission reactor near a large number of locations corresponding to a wave of burning.

In accordance with an embodiment of the present invention, there is provided a method of operating a fuel assembly of a nuclear fission reactor configured to control the removal of volatile nuclear fission products released by a combustion wave in a traveling wave fission reactor, including using a casing containing a heat generating mass of nuclear fuel that limits a large the number of interconnected pores with open cells, and the use of a fluid control unit connected to the casing m and designed to control the removal of at least a portion of the volatile fission products from the pores of the mass of nuclear fuel, and to control the removal of at least a portion of the heat released by the mass of nuclear fuel at a large number of locations corresponding to a combustion wave in a traveling fission nuclear reactor, by control the flow of fluid in a large number of areas of a nuclear fission reactor in a traveling wave, near a large number of locations corresponding to a combustion wave.

A distinctive feature of this description is the implementation, for use in a nuclear fission reactor on a traveling wave, of a casing configured to receive a porous mass of nuclear fuel containing volatile fission products.

Another distinguishing feature of this description is the implementation, for use in a traveling wave fission reactor, of a fluid control assembly connected to the casing and configured to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel.

Another distinguishing feature of this description is the implementation, for use in a nuclear fission-wave fission reactor, of a fluid control unit connected to a casing for controlled removal of at least a portion of the heat generated by the mass of nuclear fuel.

Another distinguishing feature of this description is the implementation, for use in a traveling wave fission reactor, of a dual-use circuit coupled to a casing for selectively removing volatile fission products and heat from the mass of nuclear fuel.

In addition to the foregoing, various other embodiments of the methods and / or devices are set forth and described in the text of the disclosure of the invention (for example, in the claims and / or in the detailed description) and / or in the drawings of the present invention.

All of the above is the essence of the invention and, therefore, may contain simplifications, generalizations, inclusion and / or non-inclusion of details; therefore, specialists should understand that the essence of the invention is purely illustrative and not intended to be limiting in any way. In addition to the illustrative aspects, embodiments, and features described above, additional aspects, embodiments, and features will become apparent with reference to the drawings and the following detailed description.

BRIEF DESCRIPTION OF THE DRAWINGS

Despite the fact that the description ends with the claims, more specifically indicating and clearly declaring the subject of the present invention, it should be understood that the description will be better understood from the following detailed description taken in conjunction with the accompanying drawings. In addition, the use of the same symbols in different drawings, as a rule, indicates similar or identical elements.

Figure 1 is a view in partial vertical section of a first embodiment of a fuel assembly and a nuclear fission reactor system, this view also showing volatile nuclear fission products in a large number of interconnected pores with open cells bounded by a porous mass of nuclear fuel located in the fuel assembly of a nuclear fission reactor;

Figure 2 is an enlarged view of a portion of the mass of nuclear fuel, limiting a large number of interconnected pores with open cells, shown in enlarged view for clarity, and this view also shows volatile nuclear fission products located in open cell pores;

Fig. 2A is an enlarged view of a portion of a mass of nuclear fuel with a large number of particles restricting a large number of channels between them, wherein the particles and channels are shown in enlarged view for clarity, while this view also shows volatile nuclear fission products located in the channels;

Figure 3 is a view in partial vertical section of a second embodiment of a fuel assembly and a nuclear fission reactor system;

Figure 4 is a partial vertical sectional view of a third embodiment of a fuel assembly and a nuclear fission reactor system;

5 is a partial vertical sectional view of a fourth embodiment of a fuel assembly and a nuclear fission reactor system;

Fig.6 is a view in partial vertical section of a fifth embodiment of a large number of fuel assemblies and nuclear fission reactor systems located in a sealed enclosure;

6A is a partial vertical sectional view of a first embodiment of a membrane valve having a barrier configured to break;

6B is a partial vertical sectional view of a second embodiment of a membrane valve having a barrier configured to be fractured by a piston mechanism;

Fig. 7 is a partial vertical sectional view of a sixth embodiment of a large number of fuel assemblies and nuclear fission reactor systems having parts located outside the pressurized enclosure;

Fig. 7A is a partial vertical sectional view of a first feed member, a second feed member and a fluid control subassembly functionally connected together by a Y-shaped pipe joint;

7B is a partial vertical sectional view of an inlet subassembly and an outlet subassembly coupled to a fluid control subassembly;

Fig. 7C is a partial vertical sectional view of an input subassembly connected to a porous mass of nuclear fuel and an output subassembly connected to a fluid control subassembly;

Fig. 7D is a partial vertical sectional view of a large number of inlet subassemblies connected to a mass of fuel, wherein a large number of pumps are connected to respective inlet subassemblies, and an outlet subassembly connected to a fluid control subassembly is shown;

Fig. 7E is a partial vertical sectional view of a seventh embodiment of a fuel assembly and a nuclear fission reactor system, this view also showing volatile nuclear fission products in a large number of interconnected pores with open cells bounded by a porous mass of nuclear fuel located in a large the number of fuel assemblies of a nuclear fission reactor;

Fig. 8 is a partial vertical sectional view of an eighth embodiment of a fuel assembly and a nuclear fission reactor system;

9 is a top view of a ninth embodiment of a fuel assembly and a nuclear fission reactor system;

Figure 10 is a view taken along the cut line 10-10 shown in Figure 9;

11 is a partial vertical sectional view of a tenth embodiment of a fuel assembly and a nuclear fission reactor system;

12 is a partial vertical sectional view of an eleventh embodiment of a fuel assembly and a nuclear fission reactor system;

13 is a top view of a twelfth embodiment of a fuel assembly and a nuclear fission reactor system;

Fig. 14 is a view taken along section line 14-14 of Fig. 13;

Fig is a view, partially from above, of a thirteenth embodiment of a fuel assembly and a nuclear fission reactor system;

Fig.16 is a view taken along the cut line 16-16 shown in Fig.15;

17 is a top view of a fourteenth embodiment of a fuel assembly and a nuclear fission reactor system;

Fig. 18 is a view taken along section line 18-18 of Fig. 17;

Fig. 19 is a partial vertical sectional view of a fifteenth embodiment of a fuel assembly and a nuclear fission reactor system;

FIG. 20 is a partial vertical sectional view of a sixteenth embodiment of a fuel assembly and a nuclear fission reactor system; FIG.

21A-21CQ are flowcharts of illustrative methods for assembling a fuel assembly of a nuclear fission reactor configured to control the removal of volatile nuclear fission products and heat generated by a combustion wave in a traveling wave fission reactor;

22A is a flowchart of an illustrative method for removing volatile fission products at a large number of locations corresponding to a combustion wave; and

Figa-23SK are a block diagram of illustrative methods of operation of the fuel Assembly of a nuclear fission reactor configured to remove volatile fission products and heat generated by a combustion wave in a traveling wave fission reactor.

DETAILED DESCRIPTION OF THE INVENTION

In the following detailed description, references are made to the accompanying drawings, which form part of the present description. In the drawings, such symbols usually mean similar elements, unless the context dictates otherwise. The illustrative embodiments described in the detailed description shown in the drawings and claimed in the claims are not intended to be limiting. Other embodiments may be used and other changes may be made without departing from the spirit or scope of the subject matter presented herein.

In addition, the present application uses formal headings for clarity. However, it should be understood that the headers are presented for presentation purposes, and also that various types of subject matter can be discussed throughout the application (for example, devices (a) / structures (s) can be described in the header (s) of the process (s) / operations, and / or process (s) / operations may be discussed under the heading of structures (s) / process (s); and / or descriptions of one topic may cover two or more topic headings). Thus, the use of formal headings is not intended to be in any way limiting.

In addition, the subject matter described herein sometimes illustrates various elements contained within this subject matter, or in combination with various other elements. It should be understood that such an architecture is illustrative only, and that in fact a large number of other architectures that achieve the same functionality can be implemented. In a conceptual sense, any arrangement of elements to achieve the same functionality is effectively “connected” so that the desired functionality is achieved. Therefore, any two elements combined here to achieve a specific functionality can be considered as “connected” with each other so that the desired functionality is achieved regardless of the architecture or intermediate elements. In addition, any of the two elements so combined can also be considered as “functionally connected” or “functionally connected” with the other to achieve the desired functionality, and any two elements that can be connected in this way can also be considered as “functionally connected” each with a friend to achieve the required functionality. Specific examples of functionally connected elements include, but are not limited to, physically mating and / or physically interacting elements and / or wirelessly interacting and / or wirelessly interacting elements and / or logical interacting and / or logical interacting elements .

In some cases, one or more elements may be referred to herein as "configured to". Professionals should understand that “configured to” may generally refer to items in an active state and / or items in an inactive state and / or items in standby mode unless the context otherwise requires.

The accumulation of heat during operation of the reactor can cause the fuel assembly to expand, which will lead to the displacement of the elements of the reactor core, creep of the shell of the fuel element, which can increase the risk of rupture of the shell of the fuel element and the swelling of the fuel during reactor operation. This may increase the risk that the fuel may crack or otherwise degrade. Fuel cracking may precede the failure mechanisms of the fuel element shell, such as the mechanical interaction of the fuel and the shell, and lead to the release of gaseous fission products. The release of gaseous fission products leads to higher levels of radiation than the normal level of radiation.

During the nuclear fission process, nuclear fission products are formed and can accumulate in the fuel. The accumulation of nuclear fission products, including gaseous fission products, can lead to undesirable amounts of expansion of the fuel assembly. Such expansion of the fuel assembly, in turn, may increase the risk of fuel cracking and the concomitant release of nuclear fission products into the environment. Despite the fact that the margin of safety is taken into account in the design of the reactor, and precise quality control during production reduces these risks to a minimum, in some cases it may be appropriate to reduce these risks even more.

Therefore, with reference to FIG. 1, a first embodiment of a fuel assembly and a nuclear fission reactor system, generally indicated by reference numeral 10, is shown for heat production by fissionable fissionable nuclides such as Uranium-235, Uranium-233 or Plutonium-239 , or by rapidly dividing a nuclide such as Thorium-232 or Uranus-238. From the description below, it should be understood that the fuel assembly 10 is also configured to control the removal of volatile nuclear fission products 15 created during the fission process. Volatile fission products 15 are generated by a traveling combustion wave 16, which is initiated by a relatively small and removable fission igniter 17. In this regard, a nuclear fission igniter 17 that contains moderate isotopic enrichment of a fissionable nuclear material, such as, without limitation, U-233, U-235, or Pu-239, is suitably located at a predetermined location in the fuel assembly 10. Neutrons released by the igniter 17. Neutrons that are released by the ignitor 17 are captured by fissionable and / or reproducing material in the nuclear fission fuel assembly 10 to initiate a nuclear fission chain reaction. If necessary, the igniter 17 can be removed as soon as the chain reaction becomes self-sustaining. It should be understood that volatile fission products 15 of nuclear fission 15 can be controlled in a controlled manner in response to the controlled positioning of the combustion wave 16 in the fuel assembly 10 of the nuclear fission reactor. It should be understood that any of the embodiments of the fuel assembly described in this document can be used as an element of a nuclear fission reactor on a traveling wave. Such a traveling-wave fission reactor is disclosed in detail in simultaneously pending US patent application No. 11/605943, filed November 28, 2006 in the name of Roderick A. Hyde et al. And entitled "Automated Nuclear Reactor for Longer Life", the assignee of which is the applicant of this application, and the full disclosure of which is incorporated herein by reference.

However, with reference to FIG. 1, the fuel assembly 10 comprises a casing 20 having walls 30 for tightly enclosing the porous mass 40 of nuclear fuel. The nuclear fuel mass 40 contains the aforementioned fissionable nuclide, such as Uranium-235, Uranium-233 or Plutonium-239. In addition, the nuclear fuel mass 40 may contain the aforementioned nuclides of a reproducing material, such as Thorium-232 and / or Uranium-238, which will be converted during the nuclear fission process into one or more fissionable nuclides mentioned above. Another alternative is that the nuclear fuel mass 40 may contain a pre-prepared mixture of fissile and reproducing nuclides. As described in more detail below, the nuclear fuel mass 40 is capable of producing volatile nuclear fission products 15, which may be isotopes of iodine, bromine, cesium, potassium, rubidium, strontium, xenon, krypton, barium and mixtures thereof, or other gaseous or volatile materials.

With reference again to FIG. 1, as previously mentioned, the porous mass 40 of nuclear fuel may substantially contain a metal, such as uranium, thorium, plutonium, or alloys thereof. More specifically, the nuclear fuel mass 40 may be a porous material obtained from an oxide selected from the group consisting mainly of: uranium oxide (UO), uranium dioxide (UO ₂ ), thorium dioxide (ThO ₂ ) (also known as oxide thorium), uranium trioxide (UO ₃ ), uranium oxide - plutonium oxide (UO-PuO), uranium oxide-oxide (U ₃ O ₈ ) and mixtures thereof. Alternatively, the nuclear fuel mass 40 may substantially contain uranium carbide (UC _X ) or thorium carbide (ThC _X ). For example, the nuclear fuel mass 40 may be a foam material made of carbide selected from the group consisting mainly of: uranium monocarbide (UC), uranium dicarbide (UC ₂ ), uranium and a half carbide (U ₂ C ₃ ), thorium dicarbide ( ThC ₂ ), thorium carbide (ThC) and mixtures thereof. Uranium carbide or thorium carbide can be sprayed into a matrix of niobium carbide (NbC) and zirconium carbide (ZrC) so as to form a mass of 40 nuclear fuel. The potential benefit of using niobium carbide and zirconium carbide is that they form a refractory structural substrate for uranium carbide or thorium carbide. As another example, the nuclear fuel mass 40 may be a porous material made of a nitride selected from the group consisting mainly of: uranium nitride (U ₃ N ₂ ), uranium nitride - zirconium nitride (U ₃ N ₂ -Zr ₃ N ₄ ), uranium nitride - plutonium nitride ((U-Pu) N), thorium nitride (ThN), uranium-zirconium alloy (UZr) and mixtures thereof. As best seen in FIGS. 2 and 2A, the porous mass 40 of nuclear fuel can limit a large number of interconnected pores 50c to open cells spatially distributed in the mass 40 of nuclear fuel. As used herein, the term “open cell pores” means that each pore 50 is interconnected with one or more adjacent pores 50, thereby making it possible to move a fluid, such as a gas or liquid, directly between the pores 50. That is, the pores 50c open cells are located in a mass of 40 nuclear fuel in order to form a fibrous, rod-like, spider-like or honeycomb structure. Alternatively, the nuclear fuel mass 40 may contain porous fuel material formed by a set of fuel particles 63 (eg, sintered balls or packed spheres) that define a large number of interstitial channels 65 between them. In addition, open cell pores 50c may be located in a fuel material having a combination of characteristics of foamed and porous materials. It should be understood that the description below relating to pores 50 also applies to channels 65.

With reference again to FIGS. 2 and 2A, it should be understood that the volatile fission product 15, which is generated by the combustion wave 16, may initially be present in some or all of the pores 50, and may naturally vaporize and diffuse through the casing 40 of nuclear fuel. It should also be understood that at least some pores 50 have a predetermined configuration to enable at least a portion of the volatile fission product 15 to exit the pores 50 of the porous mass 40 of nuclear fuel within a predetermined response time. The predetermined response time may be from about 10 seconds to about 1000 seconds. Alternatively, the predetermined response time may be from about one second to about 10,000 seconds, depending on the intended configuration of the pores 50.

With reference to FIG. 1, for example, via a segment 70 of a first pipe, a fluid control subassembly 80 bounding a first volume 90 containing a first fluid, such as pressurized helium gas, is connected. Alternatively, the first fluid may be any suitable inert gas under pressure, for example, without limitation, neon, argon, krypton, xenon, and mixtures thereof. Another alternative is that the first fluid may be a suitable liquid, such as liquid lead (Pb), sodium (Na), lithium (Li), mercury (Hg), or similar liquids or liquid mixtures. As described in more detail later in this document, the fluid control subassembly 80 facilitates the controlled removal of volatile nuclear fission product 15 and heat from the mass 40 of nuclear fuel. In other words, the fluid control subassembly 80 is configured to circulate the first fluid through the porous mass 40 of nuclear fuel. Thus, the heat and volatile fission product 15 are removed from the nuclear fuel mass 40 when the first fluid is circulated through the nuclear fuel mass 40.

With reference now to FIG. 3, a second embodiment of a fuel assembly and a nuclear fission reactor system, generally indicated by reference numeral 100, is shown. This second embodiment of the fuel assembly 100 is substantially the same as the first embodiment of the fuel assembly 10, except that the heat exchanger 110 is connected to the casing 20. The heat exchanger 110 comprises a shell 120 defining an interior 130 configured to receive a second fluid for cooling the first fluid, which The second one is used to remove heat and volatile products of 15 nuclear fission from the mass of 40 nuclear fuel. The second fluid has a temperature that is lower than the temperature of the first fluid. In the inner part 130 there are a large number of U-shaped tubes 132 (only one of which is shown) with two open ends. One end of the U-shaped tube 132 has an opening 134, and the other end of the U-shaped tube 132 has another hole 136. The holes 134 and 136 are in fluid communication with the first fluid occupying the first volume 90 of the fluid control subassembly 80. It should be understood that there is a density difference between the cooled portion of the first fluid located in the tubes 132 and the heated portion of the first fluid located in the porous mass 40 of nuclear fuel. This temperature difference will result in a density difference between the cooled portion of the first fluid located in the tubes 132 and the heated portion of the first fluid located in the porous mass 40 of nuclear fuel. The difference in fluid density, in turn, causes the molecules of the colder part of the fluid to exchange molecules of the hotter part of the fluid, since the cold part of the fluid is physically higher or higher than the hotter part of the fluid. Thus, the colder and hotter parts of the fluid will interchange, causing a natural convective flow that will circulate the first fluid through the fuel assembly 100 and the mass 40 of nuclear fuel. Moreover, tubes 132 are U-shaped to increase the area of the heat transfer surface to enhance natural convection. Thus, natural convection relies on the circulation of the first fluid due to the significant temperature difference between the colder and hotter first fluid. When the first fluid circulates through the tubes 132, the second fluid, which is at a substantially lower temperature than the first fluid, will be forced to enter the interior 130 through the inlet 140, for example, by means of a pump (not shown). The second fluid then exits the inner portion 130 through the outlet 150. When the second fluid enters and exits the heat exchanger 110, a second lower temperature fluid will surround a large number of U-shaped tubes 132. Thus, between the first fluid, circulating in the tubes 132, and a second fluid surrounding the tubes 132, heat transfer by conduction will occur. Thus, the heated first fluid will transfer its heat to the colder second fluid.

Referring again to FIG. 3, this second embodiment of the fuel assembly 100 may be configured to operate without any pumps or valves for circulating the first fluid, since the first fluid may be circulated by natural convection. The absence of pumps and valves can increase the reliability of the second embodiment of the fuel assembly 100 while reducing the cost of production and maintenance of the second embodiment of the fuel assembly 100.

However, still with reference to FIG. 3, if necessary, the heat exchanger 110 can serve as a steam generator. That is, depending on the temperature and pressure in the heat exchanger 110, part of the second fluid may evaporate, turning into steam (when the second fluid is water), which leaves the outlet pipe 150. The steam leaving the outlet pipe 150 may be delivered to a generator turbine (not shown) for generating electricity in a manner that is well known in the art for generating electricity from steam.

With reference to FIG. 4, a third embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated by 190, intended primarily to remove heat and volatile fission products 15 from the mass 40 of nuclear fuel. The third embodiment of the fuel assembly 190 of the nuclear fission reactor comprises a second tube segment 200, which is in communication with a first volume 90 at one end of the second tube segment 200, and is integrally connected at the other end of the second tube segment 200 to the inlet of the first pump 210, which may be a centrifugal pump. Such a pump suitable for this purpose may be of a type that may be available, for example, from Sulzer Pumps, Ltd., located in Winterthur, Switzerland. The output of the first pump 210 is connected to a third tube segment 220, which, in turn, is in communication with a mass of 40 nuclear fuel. In addition, the heat exchanger 110 may be connected to a third tube segment 220 to remove heat from a fluid flowing through a third tube segment 220.

Still referring to FIG. 4, a first pump 210 is activated to remove heat from the nuclear fuel mass 40. The first pump 210 will draw the fluid, like the previously mentioned helium gas, from the second segment 200 of the tube and thereby from the first volume 90, which is limited by the fluid control subassembly 80. The first pump 210 will pump fluid through a third tube segment 220. The fluid flowing through the third segment 220 of the tube enters a large number (or many) of the pores 50c with open cells, which are limited by the mass of 40 nuclear fuel. Fluid flowing through open cell pores 50c receives heat generated by a mass of 40 nuclear fuel. Heat is obtained by forced convective heat transfer, when the fluid is pumped through open pores 50c through the pores using the first pump 210. When the first pump 210 is running, the fluid flowing through the nuclear fuel mass 40 and experiencing convective heat transfer is extended due to the pumping action of the pump 210. through the first tube segment 70 to the first volume 90, through the second tube segment 200, and from there to the third tube segment 220, from where heat is removed by the heat exchanger 110. In addition, while the fluid I medium circulates between the mass of 40 nuclear fuel and the first volume of 90, part of the volatile products of 15 nuclear fission occurring in the mass of 40 nuclear fuel can be purged and stored in the first volume of 90, thereby removing, or at least reducing the number of products 15 nuclear fission present in the mass of 40 nuclear fuel. In this regard, the first volume 90 may be lined with nuclear fission-containing material 255, which retains nuclear fission products 15 as the fission-product-removing fluid enters the volume 90. The nuclear fission-containing material may be, with limitation, silver zeolite (AgZ) to remove xenon (Xe) and krypton (Kr), or the nuclear fission purge material can be, without limitation, metal oxides of silicon dioxide (SiO ₂ ) or titanium dioxide on (TiO ₂ ) to remove the radioisotopes of cesium (Cs), rubidium (Rb), iodine (I ₂ ), tellurium (Te) and mixtures thereof. An advantage of using this third embodiment of the fuel assembly 190 is that only pump 210 is needed to circulate the first fluid. No valves required. The absence of valves can increase the reliability of the third embodiment of the fuel assembly 190 while reducing the cost of production and maintenance of the third embodiment of the fuel assembly 190.

With reference to FIG. 5, a fourth embodiment of a fuel assembly and a nuclear fission reactor system, generally indicated at 230, is configured to further enhance the removal of the previously mentioned volatile fission products 15 as well as heat from the mass 40 of nuclear fuel. A fourth embodiment of a fuel assembly 230 of a nuclear fission reactor is substantially similar to a third embodiment of a fuel assembly 190 of a nuclear fission reactor, with the exception that means have been added to improve the removal of heat and volatile fission products 15 of nuclear fission 15. In this regard, the fourth tube segment 240 has the end is in communication with the first volume 90, and the other end is integrally connected to the inlet of the second pump 250. The outlet from the second pump 250 is integrally connected to the sixth tube segment 260. The sixth tube segment 260, in turn, is in communication with a second volume 270 bounded by the first fission product tank or tank 280. During the operation of the fourth embodiment of the fuel assembly 230, the pump 210 will pump the first fluid from the first volume 90 through the second tube segment 200, through the third tube segment 220, through the mass of nuclear fuel 40, through the first tube segment 70 and back to the first volume 90. As the first fluid flows through the third tube segment 220, the fluid the food will give its heat to the second fluid in the heat exchanger 110. The first pump 210 may then be forced to stop its work after a predetermined period of time. The second pump 250 may then be actuated to retard nuclear fission products 15, including a first fluid mixed therewith, through a fourth tube segment 240, through a fifth tube segment 260 and into a second volume 270, which is bounded by a first product tank nuclear fission, or tank 280. Thus, volatile fission products 15 will be removed from the mass 40 of nuclear fuel, and then stored in the first tank for nuclear fission products, or tank 280, for their subsequent removal outside the device or nuclear fission products 15 in the tank or tank 280 may remain in situ if necessary. In this fourth embodiment of the fuel assembly 230, only 210/250 pumps are required. No valves required. The absence of valves can increase the reliability of the fourth embodiment of the fuel assembly 230 while reducing the cost of manufacturing and maintenance of the fourth embodiment of the fuel assembly 230. Another advantage of the fourth embodiment of the fuel assembly 230 is that the fission products 15 are isolated in a second volume 270 and can be removed for subsequent removal outside the device or left in situ.

With reference to FIG. 6, a fifth embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated at 290. In this regard, a large number of fuel assemblies 290 of a nuclear fission reactor of the fifth embodiment may be provided (only three of which are shown) . A pressurized container 310, such as a pressure vessel or reactor containment container, surrounds the fuel assembly 290 of the nuclear fission reactor to prevent leakage of radioactive particles, gases, or liquids from the fuel assembly 290 into the environment. The pressurized container 310 may be steel, concrete and other materials of suitable size and thickness to reduce the risk of such radiation leaks and provide the necessary pressure loads. Although only one vessel 310 is shown, additional reactor protective containers may be provided surrounding the vessel 310, one enclosed in the other, to further ensure that no radioactive particles, gases, or liquids are leaking from the fuel assembly 290 of the nuclear fission reactor . Capacity 310 also limits the chamber 320, in which the fifth embodiment of the fuel assembly 290 of the nuclear fission reactor is located. A fifth embodiment of a fuel assembly 290 of a nuclear fission reactor is configured to manage the removal of stored heat as well as the controlled removal of volatile nuclear fission products 15, as described in more detail below.

Referring again to FIG. 6, the fuel assembly 290 comprises a compact, combined, closed dual-use loop for removing heat and volatile fission products, generally indicated at 330. The dual-use loop 330 is configured to selectively remove heat as well as volatile 15 nuclear fission products from a mass of 40 nuclear fuel. In this regard, the circuit 330 may work first to remove volatile fission products 15 and then to remove heat, or vice versa. Thus, the circuit 330 is configured to sequentially remove heat and nuclear fission products 15.

Referring again to FIG. 6, the dual-use circuit 330 comprises the previously mentioned fluid control subassembly 80 defining a first volume 90 containing a fluid source. The first tube segment 70 is in communication with the nuclear fuel mass 40 at one end of the first tube segment 70, and at the other end of the first tube segment 70 is integrally connected to the inlet of the third pump 340, which may be a centrifugal pump. The outlet of the third pump 340 is connected to the sixth tube segment 350, which, in turn, is connected to the first volume 90. The second tube segment 200 is in communication with the first volume 90 at one end of the second tube segment 200, and is integrally connected to the input of the first pump 210 at the other end of the second tube segment 200. It should be understood that pumps 340 and 210 may be selected such that either pump 340 or pump 210 alone is capable of circulating a fluid stream with a reduced but still sufficient flow rate in the dual-use circuit 330. That is, even if one of the pumps, either pump 340 or pump 210 is absent, turned off or otherwise inoperative, the dual-use circuit will still maintain the ability to circulate fluid through the dual-use circuit 330. A heat exchanger 355 is located in the third tube segment 220 between the seventh tube segment 360 and the housing 20 for removing heat from the fluid when the fluid is circulated through the dual-use circuit 330. The heat exchanger 355 may be substantially similar in configuration to the heat exchanger 110. A second tank for volatile fission products, or tank 370, is connected to any of the tube segments 70/200/220/350, for example, to the seventh tube segment 360. The second tank or tank 370, limits the third volume 380 to contain and isolate volatile fission products 15. The second tank, or tank 370, is connected to the third tube segment 220 via a seventh tube segment 360. With a seventh tube segment 360, a first engine-driven backflow preventer valve 390 is operatively connected to allow the flow of volatile fission products 15 to a third volume 380; but not allowing backward flow of nuclear fission products 15 from the third volume 380. The first engine-driven backflow prevention valve 390 may be actuated by a controller or a control unit 400 electrically connected to it. Alternatively, valve 390 need not be motor driven, but may be controlled by appropriate other means. Such a suitable backflow prevention valve can be obtained, for example, from Emerson Process Manufacture, Ltd., located in Baar, Switzerland. As described in more detail below, the volatile fission products 15 of the nuclear fissile 15 produced by the mass 40 of nuclear fuel will be captured and held in the third volume 380 to isolate the volatile fission products 15 of the nuclear fission.

Still referring to FIG. 6, a second engine-driven backflow prevention valve 410 is operatively connected to a third tube segment 220 and inserted between the first backflow prevention valve 390 and the housing 20. The second backflow prevention valve 410 allows fluid to flow into the casing 20, but does not allow a reverse flow of fluid from the casing 20 back to the third segment 220 of the tube. The second engine-driven backflow prevention valve 410 can be controlled by a control unit 400 electrically connected to it. Thus, the first tube segment 70, the third pump 340, the sixth tube segment 350, the heat exchanger 355, the fluid control subassembly 80, the second tube segment 200, the first pump 210, the third tube segment 220, the seventh tube segment 360, and the second nuclear product reservoir division, or holding tank 370, a first backflow prevention valve 390, a second backflow prevention valve 410, a control unit 400, and a nuclear fuel mass 40 together define a dual purpose circuit 330. As described in more detail in the present description, the dual-use circuit 330 is configured to circulate fluid through pores 50c with open cells of the nuclear fuel mass 40, so that heat and volatile nuclear fission products 15 are selectively removed from the nuclear fuel mass 40 sequentially or simultaneously. From the description given here it should be understood that the advantage of this fifth embodiment of the fuel assembly 290 of a nuclear fission reactor is that the dual-use circuit 330 can selectively sequentially remove volatile nuclear fission products 15 and heat by controlled operation of pumps 210/340, valves 390 / 410 and control unit 400.

Referring again to FIG. 6, a large number of neutron flux sensors or detectors 412 (only one of which is shown) can be located in the nuclear fuel mass 40 to detect various operational characteristics of the nuclear fuel mass 40. By way of example only, and not by way of limitation, the detector 412 may be configured to detect operational characteristics of the neutron population level, power level, and / or position of the combustion wave 16 in the mass 40 of nuclear fuel. The detector 412 is connected to a control unit 400 that controls the operation of the detector 412. In addition, a large number of fission pressure detectors 413 (only one of which is shown) can be located in the nuclear fuel mass 40 to detect the pressure level of the nuclear fission products in the mass 40 nuclear fuel. In addition, it should be understood that the control unit 400 is configured to control valves 390 and 410 to control the release of volatile nuclear fission products 15 and heat, depending on the amount of time during which the fuel assembly 290 of the nuclear fission reactor is constantly or periodically operating, and / or in accordance with any work schedule associated with the fuel assembly 290 of the nuclear fission reactor. A controller that can be used as a control unit 400 may be of the type that may be available, for example, from Stolley and Orlebeke, Incorporated, located in Elmhurst, Illinois, USA. Moreover, neutron flux detectors suitable for this purpose can be obtained from Thermo Fisher Scientific, Incorporated, based in Waltham, Massachusetts, USA. In addition, suitable pressure detectors can be obtained from Kaman Measuring Systems, Incorporated, based in Colorado Springs, Colorado, USA.

As shown in FIGS. 6A and 6B, a first embodiment of a diaphragm valve, generally designated 414a, having a hollow body 415, may, if necessary, replace valves 390 and / or 410. Alternatively, the previously mentioned valves 390 or 410 backflow prevention can be used in conjunction with the first embodiment of the membrane valve 414a, as shown in the drawing. Inside the hollow valve body 415 there are a large number of brittle barriers or membranes 416, which can be made of thin elastomeric material or metal of thin cross-section. Membranes 416 break or rupture when exposed to a predetermined pressure in the system. Each membrane 416 is mounted on one of a large number of supports 417, for example, by means of fastening means 418. The supports 417 are integrally connected to the valve body 415. Alternatively, any of the valves 390 or 410 may be a second embodiment of a diaphragm valve, generally indicated by reference numeral 414b, having brittle barriers or membranes 416 configured to be fractured by a piston device, generally indicated by reference numeral 419. Second an embodiment of diaphragm valve 414b may be used in conjunction with backflow prevention valves 390 or 410, as shown. The piston device 419 has a movable piston 419a movable for tearing the membrane 416. Each piston 419a is movable 419b by means of an engine. The motors 419b are connected to the control unit 400, so that the control unit 400 controls the motors 419b. Thus, each piston 419a is movable to rupture the membrane 416 by an operator action when the operator controls the control unit 400. Valves 414b may be specialized valves that can be obtained from Solenoid Solutions, Incorporated, based in Erie, Pennsylvania, USA. However, it should be understood that, if necessary, valves 414a and 414b may be non-return valves and not diaphragm valves.

Returning to FIG. 6, operation of the dual-use circuit 330 for removing volatile fission products 15 from a mass of 40 nuclear fuel will now be described. As previously mentioned, circuit 330 can operate to selectively sequentially remove volatile fission products 15 and also heat from the mass 40 of nuclear fuel. To remove volatile fission products 15 from the nuclear fuel mass 40, the first valve 390 is opened and the second valve 410 is closed, for example, by the action of a control unit 400 to which the valves 390/410 are electrically connected. As mentioned earlier, volatile fission products 15 are created in a mass of 40 nuclear fuel with a wave of 16 combustion and are located in the pores 50 with open cells 50. The third pump 340 selectively operates, for example, using the control unit 400 so that the nuclear fission products 15 obtained by the pores 50 with open cells, pass through the first tube segment 70 into the sixth tube segment 350, and then into the first volume 90. The first pump 210 will then pull the fission products 15 out of the first volume 90, and then through the second tube segment 200. The first pump 210 will pump fission products 15 from the second tube segment 200 and through the third tube segment 220. Nuclear fission products 15 flowing along the third tube segment 220 will be redirected to the second fission product tank, or tank 370, since the first valve 390 is open and the second valve 410 is closed. After a predetermined amount of time, the first valve 390 is closed and the second valve 410 is opened to resume, if necessary, removing fission products 15 from the mass 40 of nuclear fuel.

Still with reference to FIG. 6, operation of the circuit 330 for removing heat from the nuclear fuel mass 40 will be described. To remove heat from the mass 40 of nuclear fuel, the first valve 390 is closed, and the second valve 410 is opened, for example, as a result of the action of the control unit 400. The first pump 210 and the third pump 340 are driven, which may also be the action of the control unit 400. The first pump 210 draws a fluid, such as the aforementioned helium gas, through the first tube segment 200 and thereby from the first volume 90, which limited to the fluid control subassembly 80. The first pump 210 pumps fluid through a third tube segment 220. The previously mentioned heat exchanger 355 is in communication through heat transfer with a fluid flowing through a third tube segment 220 to remove heat transferred by the fluid. Fluid flowing through the third segment 220 of the tube will not be redirected to the tank or tank 370, since the first valve 390 is closed. The fluid flowing through the third segment 220 of the tube enters a large number (or many) of pores 50c with open cells, which are limited by a porous mass of 40 nuclear fuel. The fluid entering the pores 50c with open cells receives heat generated by a mass of 40 nuclear fuel. Heat is obtained by convective heat transfer when the fluid flows through open cell pores 50c. When convective heat transfer occurs in the mass 40 of nuclear fuel, the third pump 340 is driven, for example, using the control unit 400. When the third pump 340 is operating, the fluid in the mass 40 of nuclear fuel and undergoing convective heat transfer passes through the first segment 70 of the tube and into the first volume 90. The advantage of using the fifth embodiment of the fuel assembly 290 of a nuclear fission reactor is that the compact circuit Dual-use 330 can selectively sequentially remove volatile fission products 15 and then remove heat, or vice versa. This result is achieved by the controlled operation of pumps 210/340 and valves 390/410 using the control unit 400, as well as using a heat exchanger 355.

With reference to FIG. 7, a sixth embodiment of a fuel assembly and a nuclear fission reactor system is generally indicated by a reference numeral 420. A sixth embodiment of a fuel assembly 420 is substantially similar to a fifth embodiment of a fuel assembly 290, except that the following elements are located essentially outside the vessel 310: a first tube segment 70, a third pump 340, a sixth tube segment 350, a fluid control subassembly 80, a second tube segment 200, a first pump 210, a third tube segment 220, a first valve 390, heat exchanger 355, seventh tube segment 360, second tank for fission products, or tank 370, second valve 410 and control unit 400. In some cases, the placement of these elements outside the vessel 310 may make these elements more accessible for easier maintenance without exposing the equipment and reactor personnel to the radiation level inside the vessel 310 when performing such maintenance.

As shown in FIG. 7A, the first fluid supply tank, or the first element 422, the second fluid supply tank, or the second element 423, and the fluid control subassembly 80 are operatively connected by a Y-shaped pipe junction 424. The first fluid supply element 422 is configured to supply a nuclear fission product removal fluid to the fluid control subassembly 80 so as to allow the nuclear fission product removal subassembly 80 to circulate the nuclear fission product through the pores 50c with open cells of the nuclear fuel mass 40. Thus, at least a portion of the nuclear fission products 15 obtained by the pores 50 of the nuclear fuel mass 40 is removed from the pores 50, while the fluid control subunit 80 circulates the fission products removal fluid through the pores 50. In addition, the second a fluid supply element 423 that is configured to supply heat-dissipating fluid to the fluid control subassembly 80 so as to allow the heat-dissipating fluid to be circulated by the fluid control subassembly 80 through es pores mass 40 of nuclear fuel. Thus, at least a portion of the heat generated by the nuclear fuel mass 40 is removed from the nuclear fuel mass 40, while the fluid control subassembly 80 circulates heat-dissipating fluid through the nuclear fuel mass 40. The nuclear fission product removal fluid may be, but is not limited to, hydrogen (H ₂ ), helium (He), carbon dioxide (CO ₂ ) and / or methane (CH ₄ ). The heat-removing fluid may be, without limitation, hydrogen (H ₂ ), helium (He), carbon dioxide (CO ₂ ), sodium (Na), lead (Pb), potassium sodium (NaK), lithium (Li) , “Light water” (H ₂ O), lead-bismuth alloys (Pb-Bi) and / or fluorine-lithium-beryllium (F-Li-Be). The first element 422 and the second element 423 may be substantially identical in configuration. A pair of backflow prevention valves (not shown) can be integrally coupled to one of the elements 422/423 to control the flow of the nuclear fission product and the heat that removes heat to the volume 90, but allowing a backflow from the volume 90 and back to either the first element 422 or the second element 423. Thus, the first element 422 and the second element 423 are configured to supply, respectively, removing products of nuclear fission of the fluid and heat-removing fluid subassembly 80 fluid control. In other words, the first element 422 and the second element 423 are arranged for sequentially supplying, respectively, removing nuclear fission products of the fluid and removing heat of the fluid to the fluid control subassembly 80. Moreover, a pair of pumps (not shown) are connected to the first element 422 and the second element 423, respectively, for pumping a nuclear fission product and heat-removing fluid to the fluid control subassembly 80.

With reference to FIG. 7B, the fluid control subassembly may alternatively comprise an inlet subassembly 426 for supplying a nuclear fission product removal fluid to the fluid control subassembly 80. A valve 426 'may be inserted between the inlet subassembly 426 and the fluid control subassembly 80 to control the flow of the nuclear fission product removing the inlet subassembly 426 to a volume 90. A fourth pump 340', which is in communication with the volume 90, and which is connected to mass of 40 nuclear fuel, can then pump the fluid removing the nuclear fission products into the porous mass 40 of nuclear fuel. An output subassembly 427 is also provided for removing nuclear fission product removal fluid from the porous mass 40 of nuclear fuel. In this regard, the third pump 340 is configured to remove the nuclear fission product removing fluid from the nuclear fuel mass 40 and to the fluid control subassembly 80. After that, the nuclear fission product removal fluid flows into the outlet 427. Another valve 427 ′ may be inserted between the output subassembly 427 and the fluid control subassembly 80 to control the flow of the nuclear fission product deletion fluid to the output subassembly 427. During operation, when the valve 427 'is closed and the valve 426' is open, the fission product removing fluid in the input subassembly 426 is drawn by pump 340 'into a volume 90 and then into a mass of 40 nuclear fuel. After the nuclear fission product removal fluid is essentially discharged from the inlet subassembly 426, the pump 340 'ceases to operate. Valve 426 'then closes and valve 427' opens. The pump 340 is then driven to retract the nuclear fission product from the nuclear fuel mass 40 and to the volume 90. The nuclear fission product to be removed is then delivered to the output subassembly 427. A heat exchanger 355 may be inserted between the fluid control subassembly 80 and an output subassembly 427 for removing heat from the fluid, if necessary.

With reference to FIG. 7C, the fluid control subassembly may alternatively comprise an inlet subassembly 426 that is coupled to the housing 20. An additional pump 340a pumps the fission product removal fluid from the inlet 426 to the nuclear fuel mass 40 and through the tube 426 'and tube 70a. The fission product removing fluid is drawn from the nuclear fuel mass 40 and through the tube 70b, by another additional pump 340b, and then flows to the fluid control subassembly 80. From there, the fission product-removing fluid is pumped through an additional pump 340c so that the fission-product-removing fluid flows through the pipe 427 ′ to the outlet subassembly 427. If necessary, all or some of the pumps 340a, 340b and 340c can be omitted. If necessary, a heat exchanger 355 can be inserted between the fluid control subassembly 80 and the outlet subassembly 427 to remove heat from the nuclear fission product.

With reference to FIG. 7D, the fluid control subassembly may alternatively comprise a large number of output subassemblies 428a / 428b / 428c to produce nuclear fission product removal fluid from the porous nuclear fuel mass 40, and may further comprise a large number of pumps 429a / 429b / 429c connected to the respective output subnodes 428a / 428b / 428c. Pumps 429a / 429b / 429c are configured to pump the nuclear fission product removing fluid through tubes 70a / 70b / 70c to the respective output subnodes 428a / 428b / 428c. The fission product-removing fluid flows into the fluid control subassembly 80 through a pipe 71, due to the pumping action of the pump 71 '. From there, the fission product-removing fluid flows through the pipe 427 ′ to the reservoir 427 due to the pumping action of the pump 429d. If necessary, any or all of the pumps 429, 429b, 429c, 429d and 71 'may be omitted. If necessary, a heat exchanger 355 can be inserted between the fluid control subassembly 80 and the outlet subassembly 427 to remove heat from the fluid.

With reference to FIG. 7E, a seventh embodiment of a fuel assembly and a nuclear fission reactor system, generally indicated at 430, is shown for generating heat by fissionable fission nuclide. This seventh embodiment of the fuel assembly and the nuclear fission reactor system is similar to the first embodiment of the fuel assembly and the nuclear fission reactor system 10, except that there are a large number of casings 20a, 20b and 20c. Each casing 20a, 20b, and 20c is connected to the fluid control subassembly 80 using respective tube segments 72a, 72b, and 72c. The seventh embodiment of the fuel assembly and the nuclear fission reactor system 430 works in all other ways as the first embodiment of the fuel assembly and the nuclear fission reactor system 10.

With reference to Fig. 8, an eighth embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated by reference numeral 438. This eighth embodiment of a fuel assembly 438 of a nuclear fission reactor is different from a fifth embodiment of a fuel assembly 290 of a nuclear fission reactor and a sixth embodiment fuel assembly 420 of a nuclear fission reactor in that the dual-use circuit 330 is replaced by leakage of nuclear fission products, generally indicated by position 440, and a separate path of heat removal, indicated generally by reference numeral 450. The purpose of the path 450 of heat removal is to remove heat from the mass of 40 nuclear fuel. The purpose of the path 440 for the passage of nuclear fission products is to remove and isolate the volatile fission products 15 from the mass of 40 nuclear fuel. The heat transfer path 450 includes the previously mentioned fluid control subassembly 80 defining a first volume 90. The first volume 90 contains a fluid, such as helium gas, which is used to remove heat. The first tube segment 70 is in communication with the nuclear fuel mass 40 at one end of the first tube segment 70 and is integrally connected at the other end of the first tube segment 70 to the inlet of the third pump 340. The output of the third pump 340 is connected to the sixth tube segment 350, which, in in turn, is in communication with the first volume 90. The second tube segment 200 is in communication with the first volume 90 at one end of the second tube segment 200 and is integrally connected to the inlet of the first pump 210 at the other end of the second tube segment 200. The output of the first pump 210 is connected to a third tube segment 220, which, in turn, is in communication with a mass of 40 nuclear fuel. A heat exchanger 355 is connected to a third tube segment 220 to remove heat from the fluid. Thus, the first tube segment 70, the third pump 340, the sixth tube segment 350, the fluid control subassembly 80, the second tube segment 200, the first pump 210, the third tube segment 220, the nuclear fuel mass 40 itself and the heat exchanger 355 together limit the path 450 leakage of heat. As described in more detail below, the heat transfer path 450 is configured to circulate heat-removing fluid through the heat exchanger 355 and the pores 50c by open cells of the nuclear fuel mass 40 so that heat is removed from the nuclear fuel mass 40.

However, with reference to FIG. 8, the pathway 440 for the passage of nuclear fission products comprises a first flow tube 460, one end of which is in communication with the mass 40 of nuclear fuel. The other end of the first flow tube 460 is connected to the inlet of the fifth pump 470, which may be a centrifugal pump. The output of the fifth pump 470 is connected to the second flow tube 480. The second flow tube 480 is in communication with the fourth volume 490, which is limited by the third tank for nuclear fission products, or tank 500. As described in more detail below, the path 440 for the passage of nuclear fission products the ability to remove and isolate nuclear fission products 15 from the mass of 40 nuclear fuel.

With reference again to FIG. 8, the operation of the path of heat dissipation 450 to remove heat from the mass 40 of nuclear fuel will now be described. In this regard, to remove heat from the mass 40 of nuclear fuel, the first pump 210 and the third pump 340 are driven, which can be done using the control unit 400. The first pump 210 draws a heat-removing fluid, such as the previously mentioned helium gas, through the first tube segment 200 and, thus, from the first volume 90, which is limited by the fluid control subassembly 80. The first pump 210 will pump fluid through a third tube segment 220. The fluid flowing through the third segment 220 of the tube enters a large number (or many) of the pores 50c with open cells, which are limited by the mass of 40 nuclear fuel. The fluid entering the pores 50c with open cells receives heat generated by a mass of 40 nuclear fuel. Heat is acquired through convective heat transfer when the fluid flows through open cell pores 50c. When convective heat exchange occurs in the nuclear fuel mass 40, the third pump 340 is driven by, for example, a control unit 400. When the third pump 340 is running, a fluid that experiences convective heat transfer in the nuclear fuel mass 40 is drawn through the first tube segment 70 by the third pump 340, and then pumped by the third pump 340 to the first volume 90. Any of the first pump 210, third pump 340, and the fourth pump 470 may be selectively controlled by a control unit 400. The previously mentioned heat exchanger 355, which is in heat exchange communication with a fluid flowing in the third segment 220 of the tube, removes heat from the fluid. The pumps 340 and 210 are selected so that the heat-flow path 450 can be implemented in one pump 340, in one pump 210, or in pumps 340 and 210 together. In other words, the simultaneous operation of pumps 340 and 210 will remove heat at maximum speed. On the other hand, the operation of either pump 340 or pump 210 alone will pump heat-dissipating fluid at a reduced, but still sufficient speed, if any of the pumps 340 or 210 is idle or unavailable for another reason.

With reference again to FIG. 8, the operation of the second flow path 440 for removing and isolating nuclear fission products 15 from the mass 40 of nuclear fuel will now be explained. In this regard, the path of heat dissipation 450 ceases to work, for example, by turning off the pumps 210 and 340. Then, the fifth pump 470 is activated, as a result of which the fission products 15 are pulled into the first flow tube 460 and then pumped into the second flow tube 480. When volatile fission products 15 are pumped through the second flow tube 480, the fluid enters a fourth volume 490, which is bounded by a third tank for fission products, or a tank 500. Thus, fission products 15 are removed from the mass 40 of nuclear fuel and then stored in a third fission product tank or tank 500 for subsequent removal outside the device, or the fission products 15 in the tank or tank 500 may remain in situ if necessary. The path 440 for the passage of nuclear fission products and the path 450 for the removal of heat can work simultaneously or sequentially, as necessary. Moreover, from the above description, it can be understood that the fission products 15 of nuclear fission 15 can itself remove itself from the pores 50 with open cells and move to the volume 90 without the aid of the fifth pump 470 by evaporation due to the intrinsic volatility of the fission products 15. Accordingly, the path 440 for the passage of nuclear fission products can be implemented using pump 470 or without it. The fission product path 440 may use one or more controllable shutoff valves (not shown) or backflow prevention valves (also not shown) located in the flow path 440 and operably connected to the control unit 400 to further isolate the fourth volume 490.

With reference to FIGS. 9 and 10, a ninth embodiment of a fuel assembly and a nuclear fission reactor system 510 is shown. In this ninth embodiment, the fuel assembly 510 comprises a generally cylindrical casing 515 having a wall 516 to accommodate a mass of nuclear fuel 40. A nuclear fission product that has a fission product volatile 15 captured therein is pulled out of the nuclear fuel mass 40 and into the fluid control subassembly 80 by a pump 340. A heat exchanger 355 may be provided in the pipe 220 to remove heat from the fluid . The potential benefit of using a cylindrical casing 515 is its usefulness in shaping a fuel profile. The term “fuel profile” is defined in this document to denote the geometric configuration of fissile material, nuclear fuel feedstock and / or neutron moderator.

Turning now to FIG. 11, a tenth embodiment of a fuel assembly and a nuclear fission reactor system, generally indicated by reference numeral 520, is depicted. In this tenth embodiment, the fuel assembly 520 comprises a generally spherical casing 525 having a wall 526 for enclosing the mass 40 nuclear fuel. The potential benefit of using a spherical casing 525 is that its spherical shape reduces the amount of cladding material or casing 20 needed. Another potential benefit of using a spherical casing 525 is its usefulness in shaping a fuel profile.

With reference to FIG. 12, an eleventh embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated at 530. In this eleventh embodiment, the fuel assembly 530 comprises a generally hemispherical casing 540 having a wall 545 to enclose a mass of nuclear fuel 40. The potential benefit of using the hemispherical housing 540 is that it can increase the packing density of the fuel assembly in the well 320, which is limited by capacity 310. Another potential benefit of using the hemispherical housing 540 is its usefulness in shaping the fuel profile.

With reference to FIGS. 13 and 14, a twelfth embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated at 550. In this twelfth embodiment, the fuel assembly 550 includes a generally disk-shaped casing 560 having a wall 565 for enclosing a mass of 40 nuclear fuel . The potential benefit of using a disk-shaped casing 560 is its usefulness in shaping a fuel profile.

With reference to FIGS. 15 and 16, a thirteenth embodiment of a fuel assembly and a nuclear fission reactor system is generally indicated by reference numeral 570. In this thirteenth embodiment, the fuel assembly 570 comprises a polygonal casing 580 (in cross section) having a wall 585 for fencing mass 40 nuclear fuel. In this regard, the casing 580 may have a hexagonal cross-sectional shape. The potential benefit of the hexagonal cross-sectional shape of the casing 580 is that a larger number of fuel assemblies 570 can be packaged in the well 320 of the reservoir 310 than would otherwise be possible with many other geometric shapes of the fuel assembly. Another potential benefit of using a hexagonal casing 580 is its usefulness in shaping a fuel profile.

With reference to FIGS. 17 and 18, a fourteenth embodiment of a fuel assembly and a nuclear fission reactor system is generally indicated by reference numeral 590. In this fourteenth embodiment, the fuel assembly 590 comprises a box 600 of a parallelepiped shape having walls 605 for enclosing a mass of 40 nuclear fuel . The potential benefit of using the box 600 of the parallelepiped shape is that it can increase the packing density of the fuel assembly in the well 320 of the reservoir 310. Another potential benefit of using the box 600 of the parallelepiped shape is its usefulness in shaping the fuel profile.

With reference to FIG. 19, a fifteenth embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated at 610. In this regard, the nuclear fuel mass 40 may comprise one or more fuel pellets 620 embedded in the mass. Fuel pellet 620 can function as a higher density fuel element to increase the effective mass density of 40 nuclear fuel.

With reference to FIG. 20, a sixteenth embodiment of a fuel assembly and a nuclear fission reactor system is shown, generally indicated at 625. In this regard, the fluid control subassembly 80 is connected to a large number of casings 20.

Illustrative methods

Exemplary methods associated with illustrative embodiments of fuel assemblies and systems 10, 100, 190, 230, 290, 420, 430, 510, 520, 530, 550, 570, 590, 610 and 625 of a nuclear fission reactor will now be described.

With reference to FIGS. 21A-21CQ, illustrative methods for assembling a fuel assembly and a nuclear fission reactor system are shown.

With reference to FIG. 21A, an illustrative method 630 for assembling a fuel assembly of a nuclear fission reactor is started at block 640. At block 650, a casing that surrounds the porous mass of nuclear fuel is used. At a block 660, a fluid control subassembly is coupled to the housing 20 to remove at least a portion of the volatile fission products at those locations that correspond to the combustion wave. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. The execution of method 630 is terminated at block 670.

With reference to FIG. 21B, an illustrative method 671 of assembling a fuel assembly of a nuclear fission reactor is started at block 672. At block 673, a casing that surrounds the bulk of the nuclear fuel is used. At a block 674, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 675, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control subassembly. The execution of method 671 is stopped at block 676.

With reference to FIG. 21C, an illustrative method 677 for assembling a fuel assembly of a nuclear fission reactor is started at block 680. At block 690, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 700, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 710, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control subassembly. At a block 715, a control unit is coupled to provide controlled release of volatile fission products in response to a power level in a traveling wave fission reactor. The execution of method 677 is stopped at block 720.

With reference to FIG. 210, an illustrative method 730 for assembling a fuel assembly of a nuclear fission reactor is started at block 740. At block 750, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 760, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 770, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control subassembly. At a block 780, a control unit is coupled to provide controlled release of volatile fission products in response to a neutron population level in a traveling wave fission reactor. The execution of method 730 is terminated at block 790.

With reference to FIG. 21E, an illustrative method 800 for assembling a fuel assembly of a nuclear fission reactor is started at block 810. At block 820, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 830, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 840, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control assembly. At a block 850, a control unit is coupled to provide controlled release of volatile fission products in response to pressure of volatile fission products in a traveling wave nuclear fission reactor. The execution of method 800 is stopped at block 860.

With reference to FIG. 21F, an illustrative method 870 for assembling a fuel assembly of a nuclear fission reactor is started at block 880. At block 890, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 900, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 910, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control assembly. At a block 920, a control unit is coupled to provide controlled release of volatile fission products in response to a schedule associated with a traveling wave fission reactor. The execution of method 870 is stopped at block 930.

With reference to FIG. 210, an illustrative method 940 for assembling a fuel assembly of a nuclear fission reactor is started at block 950. At block 960, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 970, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 980, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control assembly. At a block 990, a control unit is coupled to provide controlled release of volatile fission products in response to the amount of time that a nuclear fission reactor is operating. The execution of method 940 is terminated at block 1000.

With reference to FIG. 21H, an illustrative method 1010 of assembling a fuel assembly of a nuclear fission reactor is started at block 1020. At block 1030, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1040, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1050, a casing is used to surround the casing of nuclear fuel. The execution of method 1010 is terminated at block 1060.

With reference to FIG. 211, an illustrative method 1070 for assembling a fuel assembly of a nuclear fission reactor is started at block 1080. At block 1090, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 1100, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 1110, a casing is used to surround the fissile material forming the mass of nuclear fuel. The execution of method 1070 is stopped at block 1120.

With reference to FIG. 2J, an illustrative method 1130 for assembling a fuel assembly of a nuclear fission reactor is started at block 1140. At block 1150, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 1160, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1170, a casing is used to surround the fissile material forming the mass of nuclear fuel. The execution of method 1130 is terminated at block 1180.

With reference to FIG. 21K, an illustrative method 1190 for assembling a fuel assembly of a nuclear fission reactor is started at block 1200. At block 1210, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 1220, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1230, a casing is used to surround fissile and reproducing material forming a mass of nuclear fuel. The execution of method 1190 is stopped at block 1240.

With reference to FIG. 211M, an illustrative method 1250 for assembling a fuel assembly of a nuclear fission reactor is started at block 1260. At block 1270, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 1280, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1290, a casing is used to provide controlled release of volatile fission products in response to a power level in a traveling wave fission reactor. The execution of method 1250 is stopped at block 1300.

With reference to FIG. 21M, an illustrative method 1310 for assembling a fuel assembly of a nuclear fission reactor is started at block 1320. At block 1330, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 1340, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1350, a casing is used to provide controlled release of volatile fission products in response to a neutron population level in a traveling wave fission reactor. The execution of method 1310 is stopped at block 1360.

With reference to FIG. 21M, an illustrative method 1370 for assembling a fuel assembly of a nuclear fission reactor is started at block 1380. At block 1390, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 1400, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1410, a casing is used to provide controlled release of volatile fission products in response to pressure of the volatile fission products in a traveling wave nuclear fission reactor. The execution of method 1370 is stopped at block 1420.

With reference to FIG. 210, an illustrative method 1430 for assembling a fuel assembly of a nuclear fission reactor is started at block 1440. At block 1450, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1460, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 1470, a casing is used to provide controlled release of volatile fission products in response to a timeline associated with a traveling wave nuclear fission reactor. The execution of method 1430 is terminated at block 1480.

With reference to FIG. 21P, an illustrative method 1490 for assembling a fuel assembly of a nuclear fission reactor is started at block 1500. At block 1510, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1520, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 1530, a casing is used to provide controlled release of volatile fission products in response to the amount of time that the traveling wave nuclear fission reactor continuously operates. The execution of method 1490 is stopped at block 1540.

With reference to FIG. 21Q, an illustrative method 1550 for assembling a fuel assembly of a nuclear fission reactor is started at block 1560. At block 1570, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1580, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1590, a casing is used to surround the porous mass of nuclear fuel in the form of a foam material that limits a large number of pores. The execution of method 1550 is stopped at block 1600.

With reference to FIG. 21R, an illustrative method 1610 for assembling a fuel assembly of a nuclear fission reactor is started at block 1620. At block 1630, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1640, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1650, a casing is used to surround a mass of nuclear fuel that limits a large number of pores, said large number of pores having a spatially inhomogeneous distribution. The execution of method 1610 is terminated at block 1660.

With reference to FIG. 21S, an exemplary method 1670 for assembling a fuel assembly of a nuclear fission reactor is started at block 1680. At block 1690, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1700, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 1710, a casing is used to surround a mass of nuclear fuel having a large number of channels. The execution of method 1670 is stopped at block 1720.

With reference to FIG. 21T, an exemplary method 1730 for assembling a fuel assembly of a nuclear fission reactor is started at block 1740. At block 1750, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1760, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1770, a casing is used to surround the porous mass of nuclear fuel having a large number of particles bounding a large number of channels between them. The execution of method 1730 is terminated at block 1790.

With reference to FIG. 21U, an illustrative method 1800 of assembling a fuel assembly of a nuclear fission reactor is started at block 1810. At block 1820, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1830, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 1840, a casing is used to surround a porous mass of nuclear fuel having a large number of pores, wherein at least one of the pores has a predetermined configuration to allow at least a portion of the volatile fission products to be released from the porous mass of nuclear fuel within a predetermined time response. The execution of method 1800 is stopped at block 1850.

With reference to FIG. 21V, an illustrative method 1860 of assembling a fuel assembly of a nuclear fission reactor is started at block 1870. At block 1880, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1890, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 1900, a casing is used to surround a porous mass of nuclear fuel having a large number of pores to permit the release of at least a portion of the volatile fission products within a predetermined response time of between about 10 seconds and about 1000 seconds. The execution of method 1860 is stopped at block 1910.

With reference to FIG. 21W, an illustrative method 1920 of assembling a fuel assembly of a nuclear fission reactor is started at block 1930. At block 1940, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1950, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1960, a casing accommodates a mass of nuclear fuel having a large number of pores to permit the release of at least a portion of the volatile nuclear products within a predetermined response time of between about 10 seconds and about 1000 seconds. The execution of method 1920 is terminated at block 1970.

With reference to FIG. 21X, an illustrative method 1971 of assembling a fuel assembly of a nuclear fission reactor is started at block 1972. At block 1973, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 1974, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 1975, a casing is used to seal the porous mass of cylindrical nuclear fuel. The execution of method 1971 is terminated at block 1976.

With reference to FIG. 21Y, an illustrative method 1980 for assembling a fuel assembly of a nuclear fission reactor is started in block 1990. In block 2000, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 2010, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2020, a casing is used to seal the porous mass of nuclear fuel having a polygonal shape. The execution of method 1980 is terminated at block 2030.

With reference to FIG. 21Z, an illustrative method 2040 for assembling a fuel assembly of a nuclear fission reactor is started at block 2050. At block 2060, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 2070, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2080, a casing is used to surround a porous casing of nuclear fuel having a large number of pores to produce volatile fission products released by a combustion wave in a traveling wave fission reactor. The execution of method 2040 is terminated at block 2090.

With reference to FIG. 21AA, an illustrative method 2100 for assembling a fuel assembly of a nuclear fission reactor is started at block 2110. At block 2120, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 2130, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2140, a casing is used to surround the porous casing of nuclear fuel having a large number of pores for transferring volatile fission products through the porous mass of nuclear fuel. The execution of method 2100 is terminated at block 2150.

With reference to FIG. 21AB, an illustrative method 2160 of assembling a fuel assembly of a nuclear fission reactor is started at block 2170. At block 2180, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 2190, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2200, a reservoir is coupled to a fluid control subassembly to produce volatile fission products. The execution of method 2160 is stopped at block 2210.

With reference to FIG. 21AC, an exemplary method 2220 for assembling a fuel assembly of a nuclear fission reactor is started at block 2230. At block 2240, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 2250, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2260, a fluid control subassembly is coupled to enable controlled release of volatile fission products in response to a position of a combustion wave in a traveling wave fission reactor. The execution of method 2220 is terminated at block 2270.

With reference to FIG. 21AD, an illustrative method for assembling a fuel assembly of a nuclear fission reactor starts at block 2290. At block 2300, a casing that surrounds the bulk of the nuclear fuel in the manner described above is used. At a block 2310, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2320, a fluid control subassembly is coupled such that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removing fluid through a porous mass of nuclear fuel, such that at least a portion of the volatile nuclear fission products is removed from the porous mass of nuclear fuel when a fluid control subunit circulates a fission product-removing fluid through a porous mass of nuclear fuel. The execution of method 2280 is stopped at block 2330.

With reference to FIG. 21AE, an illustrative method 2340 for assembling a fuel assembly of a nuclear fission reactor is started at block 2350. At block 2360, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 2370, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2380, a fluid control subassembly is coupled so that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removing fluid through a porous mass of nuclear fuel, such that at least a portion of the volatile nuclear fission products is removed from the porous mass of nuclear fuel when a fluid control subunit circulates a fission product-removing fluid through a porous mass of nuclear fuel. At a block 2390, an inlet subassembly is used to supply a nuclear fission product removing fluid to the porous mass of nuclear fuel. The execution of method 2340 is terminated at block 2400.

With reference to FIG. 21AF, an exemplary method 2410 for assembling a fuel assembly of a nuclear fission reactor is started at block 2420. At block 2430, a casing is used that surrounds the bulk of the nuclear fuel in the manner described above. At a block 2440, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2450, a fluid control subassembly is coupled so that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removing fluid through a porous mass of nuclear fuel, such that at least a portion of the volatile nuclear fission products is removed from the porous mass of nuclear fuel when a fluid control subunit circulates a fission product-removing fluid through a porous mass of nuclear fuel. At a block 2460, an inlet subassembly is used to remove the nuclear fission product removing fluid from the porous mass of nuclear fuel. The execution of method 2410 is terminated at block 2470.

With reference to FIG. 21AG, an illustrative method 2480 for assembling a fuel assembly of a nuclear fission reactor is started at block 2490. At block 2500, a casing is used that surrounds the porous mass of nuclear fuel in the manner described above. At a block 2510, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2520, a fluid control subassembly is coupled such that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removing fluid through a porous mass of nuclear fuel, such that at least a portion of the volatile nuclear fission products is removed from the porous mass of nuclear fuel when a fluid control subunit circulates a fission product-removing fluid through a porous mass of nuclear fuel. At a block 2530, a reservoir is used to produce a nuclear fission product fluid. The execution of method 2480 is terminated at block 2540.

With reference to FIG. 21AN, an illustrative method 2550 for assembling a fuel assembly of a nuclear fission reactor is started at block 2560. At block 2570, a casing is used that surrounds the porous mass of nuclear fuel in the manner described above. At a block 2580, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls fluid flow in areas of the reactor close to locations corresponding to the combustion wave. At a block 2590, a fluid control subassembly is coupled so that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removing fluid through a porous mass of nuclear fuel, such that at least a portion of the volatile nuclear fission products is removed from the porous mass of nuclear fuel when a fluid control subunit circulates a fission product-removing fluid through a porous mass of nuclear fuel. At a block 2600, a reservoir is coupled to supply a nuclear fission product fluid. The execution of method 2550 is stopped at block 2610.

With reference to FIG. 21A1, an illustrative method 2620 for assembling a fuel assembly of a nuclear fission reactor is started at block 2630. At block 2640, a casing is used that surrounds the porous mass of nuclear fuel in the same manner as previously described. At a block 2650, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2590, a fluid control subassembly is coupled so that the fuel assembly of the nuclear fission reactor is configured to circulate the gaseous fluid through the porous mass of nuclear fuel, such that at least a portion of the volatile nuclear fission products is removed from the porous mass of nuclear fuel. The execution of method 2620 is terminated at block 2670.

With reference to FIG. 21AJ, an illustrative method 2680 for assembling a fuel assembly of a nuclear fission reactor is started at block 2690. At block 2700, a casing is used that surrounds the porous mass of nuclear fuel in the same manner as previously described. At a block 2710, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2720, a fluid control subassembly is coupled so that the fluid control subassembly is configured to circulate fluid through a porous mass of nuclear fuel. The execution of method 2680 is stopped at block 2730.

With reference to FIG. 21AK, an illustrative method 2740 for assembling a fuel assembly of a nuclear fission reactor is started at block 2750. At block 2760, a casing is used that surrounds the porous mass of nuclear fuel in the manner described above. At a block 2770, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2780, the method includes attaching a pump. The execution of method 2740 is terminated at block 2790.

With reference to FIG. 21AL., An illustrative method 2800 for assembling a fuel assembly of a nuclear fission reactor is started at block 2810. At block 2820, a casing that surrounds the porous mass of nuclear fuel in the manner described above is used. At a block 2830, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2840, a pump is integrally coupled to a fluid control subassembly for circulating fluid between the fluid control subassembly and the porous mass of nuclear fuel. The execution of method 2800 is terminated at block 2850.

With reference to FIG. 21AM, an illustrative method 2860 of assembling a fuel assembly of a nuclear fission reactor is started at block 2870. At block 2880, a casing is used that surrounds the porous mass of nuclear fuel in the same manner as previously discussed. At a block 2890, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2900, the method includes attaching a valve. The execution of method 2860 is terminated at block 2910.

With reference to FIG. 21AM, an illustrative method 2920 for assembling a fuel assembly of a nuclear fission reactor is started at block 2930. At block 2940, a casing is used that surrounds the porous mass of nuclear fuel in the same manner as previously discussed. At a block 2950, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 2960, a valve is placed between the housing and the fluid control subassembly to control fluid flow between the casing and the fluid control subassembly. The execution of method 2920 is stopped at block 2970.

With reference to FIG. 21AO, an illustrative method 2980 for assembling a fuel assembly of a nuclear fission reactor is started at block 2990. At block 3000, a casing is used that surrounds the porous mass of nuclear fuel in the manner described above. At a block 3010, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 3020, a valve is placed between the housing and the fluid control subassembly to control fluid flow between the casing and the fluid control subassembly. At a block 3030, a backflow prevention valve is placed between the housing and the fluid control subassembly. The execution of method 2980 is stopped at block 3040.

With reference to FIG. 21AP, an illustrative method 3050 for assembling a fuel assembly of a nuclear fission reactor is started at block 3060. At block 3070, a casing is used that surrounds the porous mass of nuclear fuel in the manner described above. At a block 3080, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 3090, the method includes attaching a barrier configured for controlled destruction. The execution of method 3050 is stopped at block 3100.

With reference to FIG. 21AQ, an illustrative method 3110 for assembling a fuel assembly of a nuclear fission reactor is started at block 3120. At block 3130, a casing is used that surrounds the porous mass of nuclear fuel in the same manner as previously described. At a block 3140, a fluid control subassembly is coupled to the casing to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 3150, a barrier capable of controlled destruction is placed between the casing and the fluid control subassembly. The execution of method 3110 is terminated at block 3160.

With reference to FIG. 21AR, an illustrative method 3170 for assembling a fuel assembly of a nuclear fission reactor is started at block 3180. At block 3190, a casing is used that surrounds the porous mass of nuclear fuel in the manner described above. At a block 3200, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 3210, a barrier capable of controlled disruption is placed between the casing and the fluid control subassembly. At a block 3220, a barrier configured to break at a predetermined pressure is placed between the housing and the fluid control subassembly. The execution of method 3170 is stopped at block 3230.

With reference to FIG. 21AS, an illustrative method 3240 for assembling a fuel assembly of a nuclear fission reactor is started at block 3250. At block 3260, a casing is used that surrounds the porous mass of nuclear fuel in the same manner as previously described. At a block 3270, a fluid control subassembly is coupled to the enclosure to remove at least a portion of the volatile fission products, as discussed previously. The fluid control subassembly controls the flow of fluid in regions of the reactor close to locations corresponding to the combustion wave. At a block 3280, a barrier capable of controlled disruption is placed between the casing and the fluid control subassembly. At a block 3290, a barrier configured to break through an operator is placed between the housing and the fluid control subassembly. The execution of method 3240 is terminated at block 3300.

With reference to FIG. 21AT, an illustrative method 3310 of assembling a fuel assembly of a nuclear fission reactor is started at block 3320. At block 3330, a casing is used to surround the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 3340, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at those locations that correspond to the combustion wave of the nuclear reactor fission on a traveling wave, by controlling the flow of fluid in areas of a nuclear fission reactor on a traveling wave located near locations corresponding to a combustion wave. The execution of method 3310 is stopped at block 3350,

With reference to FIG. 21AU, an illustrative method 3360 of assembling a fuel assembly of a nuclear fission reactor is started at block 3370. At block 3380, a casing is used to accommodate the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 3390, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat from the nuclear fuel mass at those locations that correspond to the combustion wave of the nuclear fission reactor by traveling wave, by controlling the flow of fluid in the areas of the nuclear fission reactor on a traveling wave located near the locations corresponding to the combustion wave. At a block 3400, a control unit is coupled to the fluid control subassembly to control the operation of the fluid control assembly. The execution of method 3360 is stopped at block 3410.

With reference to FIG. 21AV, an illustrative method 3420 for assembling a fuel assembly of a nuclear fission reactor is started at block 3430. At block 3440, a casing is used to accommodate the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 3450, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat from the nuclear fuel mass at those locations that correspond to the combustion wave of the nuclear fission reactor by traveling wave, by controlling the flow of fluid in the areas of the nuclear fission reactor on a traveling wave located near the locations corresponding to the combustion wave. At a block 3460, a casing is used to accommodate a mass of nuclear fuel. The execution of method 3420 is stopped at block 3470.

With reference to FIG. 21AW, an illustrative method 3480 for assembling a fuel assembly of a nuclear fission reactor is started at block 3490. At block 3500, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 3510, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat from the nuclear fuel mass at those locations that correspond to the combustion wave of the nuclear fission reactor by traveling wave, by controlling the flow of fluid in the areas of the nuclear fission reactor on a traveling wave located near the locations corresponding to the combustion wave. At a block 3520, a casing is used to accommodate fissile material forming a mass of nuclear fuel. The execution of method 3480 is terminated at block 3530.

With reference to FIG. 21AX, an illustrative method 3540 for assembling a fuel assembly of a nuclear fission reactor is started at block 3550. At block 3560, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 3570, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat from the nuclear fuel mass at those locations that correspond to the combustion wave of the nuclear fission reactor by traveling wave, by controlling the flow of fluid in the areas of the nuclear fission reactor on a traveling wave located near the locations corresponding to the combustion wave. At a block 3580, a casing is used to accommodate reproduction material forming a mass of nuclear fuel. The execution of method 3540 is stopped at block 3590.

With reference to FIG. 21AY, an illustrative method 3600 for assembling a fuel assembly of a nuclear fission reactor is started at block 3610. At block 3620, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 3630, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat from the nuclear fuel mass at those locations that correspond to the combustion wave of the nuclear fission reactor by traveling wave, by controlling the flow of fluid in the areas of the nuclear fission reactor on a traveling wave located near the locations corresponding to the combustion wave. At a block 3640, a casing is used to contain a mixture of fissile and reproducing material forming a mass of nuclear fuel. The execution of method 3600 is terminated at block 3650.

With reference to FIG. 21AZ, an illustrative method 3660 for assembling a fuel assembly of a nuclear fission reactor is started at block 3670. At block 3680, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 3690, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 3700, a fluid control subassembly is coupled to provide controlled release of volatile fission products in response to the position of the combustion wave in the traveling wave fission reactor. The execution of method 3660 is stopped at block 3710.

With reference to FIG. 21BA, an illustrative method 3720 for assembling a fuel assembly of a nuclear fission reactor is started at block 3730. At block 3740, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 3750, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 3760, a fluid control subassembly is coupled to provide controlled release of volatile fission products in response to a power level in a traveling wave fission reactor. The execution of method 3720 is stopped at block 3770.

With reference to FIG. 21BB, an illustrative method 3780 for assembling a fuel assembly of a nuclear fission reactor is started at block 3790. At block 3800, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 3810, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 3820, a fluid control subassembly is coupled so as to provide controlled release of volatile fission products in response to a neutron population level in the traveling wave fission reactor. The execution of method 3780 is stopped at block 3830.

With reference to FIG. 21BC, an illustrative method 3840 for assembling a fuel assembly of a nuclear fission reactor is started at block 3850. At block 3860, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 3870, a fluid control subassembly is coupled to the casing to control removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 3880, a fluid control subassembly is coupled to provide controlled release of volatile fission products in response to a pressure level of volatile fission products in a traveling wave nuclear fission reactor. The execution of method 3840 is stopped at block 3890.

With reference to FIG. 21BD, an illustrative method 3900 of assembling a fuel assembly of a nuclear fission reactor is started at block 3910. At block 3920, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 3930, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 3940, a fluid control subassembly is coupled so as to provide controlled release of volatile fission products in response to a timeline associated with the traveling wave fission reactor. The execution of method 3900 is stopped at block 3950.

With reference to FIG. 21BE, an illustrative method 3960 of assembling a fuel assembly of a nuclear fission reactor is started at block 3970. At block 3980, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 3990, a fluid control subassembly is coupled to the casing to control removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4000, a fluid control subassembly is coupled so as to provide controlled release of volatile fission products in response to the amount of time that the traveling wave fission reactor is operating. The execution of method 3960 is stopped at block 4010.

With reference to FIG. 21BF, an illustrative method 4020 for assembling a fuel assembly of a nuclear fission reactor is started at block 4030. At block 4040, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4050, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4060, a reservoir is coupled to a fluid control subassembly to produce volatile fission products. The execution of method 4020 is terminated at block 4070.

With reference to FIG. 21BG, an illustrative method 4080 for assembling a fuel assembly of a nuclear fission reactor is started at block 4090. At block 4100, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4110, a fluid control subassembly is coupled to the casing to control removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4120, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the volatile nuclear fission products is removed from the pores of the nuclear fuel mass, while the control subassembly a fluid circulates a fission product removing fluid through the pores of the mass of nuclear fuel. The execution of method 4080 is terminated at block 4130.

With reference to FIG. 21BH, an illustrative method 4140 for assembling a fuel assembly of a nuclear fission reactor is started at block 4150. At block 4160, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 4170, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4175, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the volatile nuclear fission products is removed from the pores of the nuclear fuel mass, while the control subassembly a fluid circulates a fission product removing fluid through the pores of the mass of nuclear fuel. At a block 4180, an inlet subassembly is used to supply a nuclear fission product to the pores of the mass of nuclear fuel. The execution of method 4140 is terminated at block 4190.

With reference to FIG. 21BI, an illustrative method 4200 of assembling a fuel assembly of a nuclear fission reactor is started at block 4210. At block 4220, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4230, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4240, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the volatile nuclear fission products is removed from the pores of the nuclear fuel mass, while the control subassembly a fluid circulates a fission product removing fluid through the pores of the mass of nuclear fuel. At a block 4250, an output subassembly is used to remove the nuclear fission product removing fluid from the pores of the nuclear fuel mass. The execution of method 4200 is terminated at block 4260.

With reference to FIG. 21BJ, an illustrative method 4270 for assembling a fuel assembly of a nuclear fission reactor is started at block 4280. At block 4290, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4300, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4310, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat produced by the nuclear fuel mass is removed from the nuclear fuel mass, while a fluid control subassembly circulates a fission product-removing fluid through the pores of the mass of nuclear fuel. The execution of method 4270 is stopped at block 4320.

With reference to FIG. 21BK, an illustrative method 4330 for assembling a fuel assembly of a nuclear fission reactor is started at block 4340. At block 4350, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4360, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4370, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat produced by the nuclear fuel mass is removed from the nuclear fuel mass, a fluid control subassembly circulates a fission product-removing fluid through the pores of the mass of nuclear fuel. At a block 4380, a reservoir is coupled to a fluid control subassembly to produce heat-removing fluid. The execution of method 4330 is stopped at block 4390.

With reference to FIG. 21BL, an illustrative method 4400 for assembling a fuel assembly of a nuclear fission reactor is started at block 4410. At block 4420, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4430, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4440, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat produced by the nuclear fuel mass is removed from the nuclear fuel mass, while a fluid control subassembly circulates a fission product-removing fluid through the pores of the mass of nuclear fuel. At a block 4450, the reservoir is coupled to a fluid control subassembly to supply heat-removing fluid. The execution of method 4400 is stopped at block 4460.

With reference to FIG. 21BM, an illustrative method 4470 for assembling a fuel assembly of a nuclear fission reactor is started at block 4480. At block 4490, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4500, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4510, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass so that at least a portion of the heat produced by the nuclear fuel mass is removed from the nuclear fuel mass while a fluid control subassembly circulates a fission product-removing fluid through the pores of the mass of nuclear fuel. At a block 4520, a radiator is coupled to a fluid control subassembly so that the radiator is in communication through heat transfer to a heat-removing fluid to remove heat from the heat-removing fluid. The execution of method 4470 is stopped at block 4530.

With reference to FIG. 21BM, an illustrative method 4540 for assembling a fuel assembly of a nuclear fission reactor is started at block 4550. At block 4560, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4570, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4580, a fluid control subassembly is configured to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat produced by the nuclear fuel mass is removed from the nuclear fuel mass, while a fluid control subassembly circulates a fission product-removing fluid through the pores of the mass of nuclear fuel. At a block 4590, a heat exchanger is coupled to the fluid control subassembly so that the heat exchanger is in communication by heat transfer to a heat-dissipating fluid to remove heat from the heat-dissipating fluid. The execution of method 4540 is stopped at block 4600.

With reference to FIG. 21BO, an illustrative method 4610 of assembling a fuel assembly of a nuclear fission reactor is started at block 4620. At block 4630, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4640, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4650, a fluid control subassembly is coupled so as to simultaneously circulate the fission product-removing product fluid and the heat-removing fluid. The execution of method 4610 is stopped at block 4660.

With reference to FIG. 21BP, an illustrative method 4670 for assembling a fuel assembly of a nuclear fission reactor is started at block 4680. At block 4690, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 4700, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4710, a fluid control subassembly is coupled so as to sequentially circulate fission product-removing product fluid and heat-removing fluid. The execution of method 4670 is stopped at block 4720.

With reference to FIG. 21BQ, an illustrative method 4730 for assembling a fuel assembly of a nuclear fission reactor is started at block 4740. At block 4750, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4760, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4770, a pump is integrally coupled to a fluid control subassembly for pumping fluid from the fluid control subassembly to the pores of the mass of nuclear fuel. The execution of method 4730 is terminated at block 4780.

With reference to FIG. 21BR, an illustrative method 4790 for assembling a fuel assembly of a nuclear fission reactor is started at block 4800. At block 4810, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 4820, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4830, the method includes attaching a pump. The execution of method 4790 is stopped at block 4840.

With reference to FIG. 21BS, an illustrative method 4850 for assembling a fuel assembly of a nuclear fission reactor is started at block 4860. At block 4870, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 4880, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4890, a fission product reservoir is coupled to a fluid control subassembly to produce volatile fission products. The execution of method 4850 is terminated at block 4900.

With reference to FIG. 21BT, an illustrative method 4910 of assembling a fuel assembly of a nuclear fission reactor is started at block 4920. At block 4930, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 4940, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 4950, a large number of first elements are coupled so as to allow the fluid control subassembly to circulate the nuclear fission product removing through the pores of the nuclear fuel mass, whereby at least a portion of the volatile nuclear fission products is removed from the pores of the nuclear fuel mass, while the fluid control subassembly circulates the removal of nuclear fission products of the fluid through the pores of the mass of nuclear fuel. The execution of method 4910 is stopped at block 4960.

With reference to FIG. 21BU, an illustrative method 4970 for assembling a fuel assembly of a nuclear fission reactor is started at block 4980. At block 4990, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5000, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5010, a large number of first elements are connected so as to allow the fluid control subassembly to circulate the nuclear fission product removing through the pores of the nuclear fuel mass, whereby at least a portion of the volatile nuclear fission products is removed from the pores of the nuclear fuel mass, while the fluid control subassembly circulates the removal of nuclear fission products of the fluid through the pores of the mass of nuclear fuel. At a block 5020, a large number of second elements are connected so as to allow the fluid control subassembly to circulate heat-removing fluid through the pores of the nuclear fuel mass, whereby at least a portion of the heat generated by the nuclear fuel mass is removed from the pores of the nuclear fuel mass, while the fluid control subassembly circulates heat dissipating fluid through the pores of the mass of nuclear fuel. The execution of method 4970 is stopped at block 5030.

With reference to FIG. 21BV, an illustrative method 5040 for assembling a fuel assembly of a nuclear fission reactor is started at block 5050. At block 5060, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5070, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5080, a large number of first elements are coupled so as to allow the fluid control subassembly to circulate the nuclear fission product-removing fluid through the pores of the nuclear fuel mass, whereby at least a portion of the volatile nuclear fission products is removed from the pores of the nuclear fuel mass, while the fluid control subassembly circulates the removal of nuclear fission products of the fluid through the pores of the mass of nuclear fuel. At a block 5090, a large number of second elements are connected so as to allow the fluid control subassembly to circulate heat-removing fluid through the pores of the nuclear fuel mass, whereby at least a portion of the heat generated by the nuclear fuel mass is removed from the pores of the nuclear fuel mass, while the fluid control subassembly circulates heat dissipating fluid through the pores of the mass of nuclear fuel. At a block 5100, the method includes interconnecting the first elements and the second elements so that at least one of the first elements and at least one of the second elements are identical. The execution of method 5040 is stopped at block 5110.

With reference to FIG. 21BW, an illustrative method 5120 for assembling a fuel assembly of a nuclear fission reactor is started at block 5130. At block 5140, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5150, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At 5160, the method includes attaching a dual-use loop for selectively removing volatile fission products and heat from nuclear fuel. The execution of method 5120 is stopped at block 5170.

With reference to FIG. 21BX, an illustrative method 5180 of assembling a fuel assembly of a nuclear fission reactor is started at block 5190. At block 5200, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5210, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5220, a fluid control subassembly is coupled so that the fuel assembly of the nuclear fission reactor is configured to circulate gas through the pores of the mass of nuclear fuel. The execution of method 5180 is terminated at block 5230.

With reference to FIG. 21BY, an illustrative method 5240 for assembling a fuel assembly of a nuclear fission reactor is started at block 5250. At block 5260, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5270, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5280, a fluid control subassembly is attached such that the fuel assembly of the nuclear fission reactor is configured to circulate fluid through the pores of the mass of nuclear fuel. The execution of method 5240 is terminated at block 5290.

With reference to FIG. 21BZ, an illustrative method 5300 of assembling a fuel assembly of a nuclear fission reactor is started at block 5310. At block 5320, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5330, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5340, a casing is used to accommodate a mass of nuclear fuel made in the form of a foam material that limits a large number of pores. The execution of method 5300 is stopped at block 5350.

With reference to FIG. 21CA, an illustrative method 5360 of assembling a fuel assembly of a nuclear fission reactor is started at block 5370. At block 5380, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5390, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5400, a casing is used so as to accommodate a mass of nuclear fuel having a large number of channels. The execution of method 5360 is stopped at block 5410.

With reference to FIG. 21CB, an illustrative method 5420 for assembling a fuel assembly of a nuclear fission reactor is started at block 5430. At block 5440, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 5450, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5460, a casing is used so as to accommodate a mass of nuclear fuel having a large number of channels. At a block 5470, a casing is used so as to accommodate a mass of nuclear fuel having a large number of particles bounding a large number of channels between them. The execution of method 5420 is terminated at block 5480.

With reference to FIG. 21CC, an illustrative method 5490 of assembling a fuel assembly of a nuclear fission reactor is started at block 5500. At block 5510, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5520, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5530, a casing is used so as to accommodate a mass of nuclear fuel that limits a large number of pores, said large number of pores having a spatially inhomogeneous distribution. The execution of method 5490 is terminated at block 5540.

With reference to FIG. 21CD, an illustrative method 5550 for assembling a fuel assembly of a nuclear fission reactor is started at block 5560. At block 5570, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 5580, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5590, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores to produce volatile nuclear fission products released by a combustion wave in a traveling wave nuclear fission reactor. The execution of method 5550 is stopped at block 5600.

With reference to FIG. 21CE, an illustrative method 5610 for assembling a fuel assembly of a nuclear fission reactor is started at block 5620. At block 5630, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5640, a fluid control subassembly is coupled to the casing to control removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5650, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores, wherein one or more of the large number of pores has a predetermined configuration to allow at least a portion of the volatile fission products to be released from the mass of nuclear fuel into for a predetermined response time. The execution of method 5610 is terminated at block 5660.

With reference to FIG. 21CF, an illustrative method 5670 for assembling a fuel assembly of a nuclear fission reactor is started at block 5680. At block 5690, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5700, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5710, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores so that at least a portion of the volatile fission products from the nuclear fuel mass can be released within a predetermined response time of between about 10 seconds and about 1000 seconds. The execution of method 5670 is stopped at block 5720.

With reference to FIG. 21CG, an illustrative method 5730 for assembling a fuel assembly of a nuclear fission reactor is started at block 5740. At block 5750, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5760, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5770, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores to allow at least a portion of the volatile fission products to be released from the nuclear fuel mass within a predetermined response time of between about one second and about 10,000 seconds. The execution of method 5730 is terminated at block 5780.

With reference to FIG. 21CH, an illustrative method of assembling a fuel assembly of a nuclear fission reactor starts at block 5800. At block 5810, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 5820, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5830, a casing is used so as to accommodate a mass of nuclear fuel with a large number of pores for transferring volatile fission products through the mass of nuclear fuel. The execution of method 5790 is stopped at block 5840.

With reference to FIG. 21CI, an illustrative method 5850 for assembling a fuel assembly of a nuclear fission reactor is started at block 5860. At block 5870, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 5880, a fluid control subassembly is coupled to the housing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5890, a casing is used so as to hermetically accommodate a cylindrical mass of nuclear fuel. The execution of method 5850 is terminated at block 5900.

With reference to FIG. 21CJ, an illustrative method 5910 of assembling a fuel assembly of a nuclear fission reactor is started at block 5920. At block 5930, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 5940, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 5950, a casing is used so as to hermetically accommodate a polygonal mass of nuclear fuel. The execution of method 5910 is stopped at block 5960.

With reference to FIG. 21SC, an illustrative method for assembling a fuel assembly of a nuclear fission reactor is started at block 5980. At block 5990, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 6000, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At block 6010, the method includes attaching a valve. The execution of method 5970 is stopped at block 6020.

With reference to FIG. 21CL., An illustrative method 6030 for assembling a fuel assembly of a nuclear fission reactor is started at block 6040. At block 6050, a casing is used to receive a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 6060, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 6070, a valve is placed between the housing and the fluid control subassembly to control fluid flow between the casing and the fluid control subassembly. The execution of method 6030 is stopped at block 6080.

With reference to FIG. 21CM, an illustrative method 6090 for assembling a fuel assembly of a nuclear fission reactor is started at block 6100. At block 6110, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 6120, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 6130, a valve is placed between the housing and the fluid control subassembly to control fluid flow between the casing and the fluid control subassembly. At a block 6140, the method includes placing a backflow prevention valve. The execution of method 6090 is stopped at block 6150.

With reference to FIG. 21CN, an illustrative method 6160 for assembling a fuel assembly of a nuclear fission reactor is started at block 6170. At block 6180, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 6190, a fluid control subassembly is coupled to the casing to control removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 6200, the method includes attaching a barrier configured for controlled destruction. The execution of method 6160 is terminated at block 6210.

With reference to FIG. 21CO, an illustrative method for assembling a fuel assembly of a nuclear fission reactor is started at block 6230. At block 6240, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores to open cells. At a block 6250, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 6260, a controlled fracture barrier is interposed between the housing and the fluid control subassembly. The execution of method 6220 is terminated at block 6270.

With reference to Fig. 21CP, an illustrative method 6280 for assembling a fuel assembly of a nuclear fission reactor is started at block 6290. At block 6300, a casing is used to receive the heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 6310, a fluid control subassembly is coupled to the casing to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 6320, a controlled fracture barrier is placed between the casing and the fluid control subassembly. At a block 6330, the method includes placing a barrier configured to control destruction at a given pressure. The execution of method 6280 is stopped at block 6340.

With reference to FIG. 21CQ, an illustrative method 6350 for assembling a fuel assembly of a nuclear fission reactor is started at block 6360. At block 6370, a casing is used to receive the heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 6380, a fluid control subassembly is coupled to the casing to control removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass, as previously mentioned. At a block 6390, a controlled fracture barrier is placed between the casing and the fluid control subassembly. At block 6400, the method includes placing a barrier configured to control destruction by an operator. The execution of method 6350 is stopped at block 6410.

With reference to Figa illustrates an illustrative method of removing volatile fission products in a large number of locations corresponding to the combustion wave. In this regard, an exemplary method 6420 for removing volatile nuclear fission products is started at block 6430. At block 6440, the removal of volatile nuclear fission products is controlled at a large number of locations corresponding to a combustion wave, a traveling fission nuclear fission reactor, by controlling the flow of fluid in a large number of areas a nuclear reactor near a large number of locations corresponding to a combustion wave. The execution of method 6420 is stopped at block 6450.

With reference to FIGS. 23-23SK, illustrative methods for controlling a fuel assembly and a nuclear fission reactor system are shown.

With reference to FIG. 23A, an illustrative method 6460 for controlling a fuel assembly of a nuclear fission reactor is started at block 6470. At block 6480, a casing is used that surrounds a porous mass of nuclear fuel having a volatile fission product. At a block 6490, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. The execution of method 6460 is stopped at block 6500.

With reference to FIG. 23B, an illustrative method 6510 for controlling a fuel assembly of a nuclear fission reactor is started at block 6520. At block 6530, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6540, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6550, the operation of the fluid control subassembly is controlled by controlling a control unit connected to the fluid control subassembly. The execution of method 6510 is stopped at block 6560.

With reference to FIG. 23C, an illustrative method 6570 for controlling a fuel assembly of a nuclear fission reactor is started at block 6580. At block 6590, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6600, a fluid control subassembly coupled to the enclosure is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6610, the operation of the fluid control subassembly is controlled by controlling a control unit coupled to the fluid control subassembly. At a block 6620, the operation of the fluid control subassembly is controlled by controlling the control unit to enable controlled release of volatile fission products in response to a power level in a traveling wave nuclear fission reactor. The execution of method 6570 is stopped at block 6630.

With reference to FIG. 230, an illustrative method 6640 for controlling a fuel assembly of a nuclear fission reactor is started at block 6650. At block 6660, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6670, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6680, the operation of the fluid control subassembly is controlled by controlling a control unit coupled to the fluid control subassembly. At a block 6690, the operation of the fluid control subassembly is controlled by controlling the control unit to enable controlled release of volatile fission products in response to a neutron population level in a traveling wave fission reactor. The execution of method 6640 is terminated at block 6700.

With reference to FIG. 23E, an illustrative method 6710 for controlling a fuel assembly of a nuclear fission reactor is started at block 6720. At block 6730, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6740, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6750, the operation of the fluid control subassembly is controlled by controlling a control unit connected to the fluid control subassembly. At a block 6760, the operation of the fluid control subassembly is controlled by controlling the control unit to enable controlled release of volatile fission products in response to pressure of the volatile fission products in a traveling wave nuclear fission reactor. The execution of method 6710 is terminated at block 6770.

With reference to FIG. 23F, an illustrative method 6780 for controlling a fuel assembly of a nuclear fission reactor is started at block 6790. At block 6800, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6810, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6820, the operation of the fluid control subassembly is controlled by controlling a control unit connected to the fluid control subassembly. At a block 6830, the operation of the fluid control subassembly is controlled by controlling the control unit to enable controlled release of volatile fission products in response to a timeline associated with a traveling wave nuclear fission reactor. The execution of method 6780 is stopped at block 6840.

With reference to FIG. 23G, an illustrative method 6850 for controlling a fuel assembly of a nuclear fission reactor is started at block 6860. At block 6870, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6880, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6890, the operation of the fluid control subassembly is controlled by controlling a control unit connected to the fluid control subassembly. At a block 6900, the operation of the fluid control subassembly is controlled by controlling the control unit to allow controlled release of volatile fission products in response to the amount of time that the traveling wave nuclear fission reactor is operating. The execution of method 6850 is stopped at block 6910.

With reference to FIG. 23H, an illustrative method 6920 for controlling a fuel assembly of a nuclear fission reactor is started at block 6930. At block 6940, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 6950, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 6960, a casing is used to accommodate a porous mass of nuclear fuel. The execution of method 6920 is stopped at block 6970.

With reference to FIG. 23I, an illustrative method 6980 for controlling a fuel assembly of a nuclear fission reactor is started at block 6990. At block 7000, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7010, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7020, a casing is used so as to accommodate fissile material forming a porous mass of nuclear fuel. The execution of method 6980 is stopped at block 7030.

With reference to FIG. 23J, an illustrative method 7040 for controlling a fuel assembly of a nuclear fission reactor is started at block 7050. At block 7060, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7070, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7080, a casing is used so as to accommodate reproduction material forming a porous mass of nuclear fuel. The execution of method 7040 is stopped at block 7090.

With reference to FIG. 23K, an illustrative method 7100 for controlling a fuel assembly of a nuclear fission reactor is started at block 7110. At block 7120, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7130, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7140, a casing is used so as to accommodate a mixture of fissile and reproducing material forming a porous mass of nuclear fuel. The execution of method 7100 is terminated at block 7150.

With reference to FIG. 23L, an illustrative method 7160 for controlling a fuel assembly of a nuclear fission reactor is started at block 7170. At block 7180, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7190, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7200, a fluid control subassembly is used to provide controlled release of volatile fission products in response to a position of a combustion wave in a traveling wave fission reactor. The execution of method 7160 is stopped at block 7210.

With reference to FIG. 23M, an illustrative method 7220 for controlling a fuel assembly of a nuclear fission reactor is started at block 7230. At block 7240, a casing that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product is used. At a block 7250, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7260, a casing is used in such a way as to accommodate a porous mass of nuclear fuel in the form of a foam material that limits a large number of pores. The execution of method 7220 is terminated at block 7270.

With reference to FIG. 23N, an illustrative method 7280 for controlling a fuel assembly of a nuclear fission reactor is started at block 7290. At block 7300, a casing that surrounds a porous mass of nuclear fuel having a volatile fission product is used. At a block 7310, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7320, a casing is used to contain a porous mass of nuclear fuel that limits a large number of pores, said large number of pores having a spatially inhomogeneous distribution. The execution of method 7280 is stopped at block 7330.

With reference to FIG. 23O, an illustrative method 7340 for controlling a fuel assembly of a nuclear fission reactor is started at block 7350. At block 7360, a casing that surrounds a porous mass of nuclear fuel having a volatile fission product is used. At a block 7370, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7380, a casing is used so as to accommodate a porous mass of nuclear fuel having a large number of channels. The execution of method 7340 is stopped at block 7390.

With reference to FIG. 23P, an illustrative method 7400 for controlling a fuel assembly of a nuclear fission reactor is started at block 7410. At block 7420, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7430, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7440, a casing is used so as to accommodate a porous mass of nuclear fuel having a large number of channels. At a block 7450, a casing is used so as to accommodate a porous mass of nuclear fuel with a large number of particles restricting a large number of channels between them. The execution of method 7400 is terminated at block 7460.

With reference to FIG. 23Q, an illustrative method 7470 for controlling a fuel assembly of a nuclear fission reactor is started at block 7480. At block 7490, a casing is used that surrounds a porous mass of nuclear fuel having a volatile fission product. At a block 7500, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7510, a casing is used to accommodate a porous mass of nuclear fuel having a large number of pores, wherein at least one of the pores has a predetermined configuration to allow at least a portion of the volatile fission products to be released from the porous mass of nuclear fuel during predefined response time. The execution of method 7470 is stopped at block 7520.

With reference to FIG. 23R, an illustrative method 7530 for controlling a fuel assembly of a nuclear fission reactor is started at block 7540. At block 7550, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7560, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7570, a casing is used so as to accommodate a porous mass of nuclear fuel having a large number of pores to permit the release of at least a portion of the volatile fission products within a predetermined response time of between about 10 seconds and about 1000 seconds. The execution of method 7530 is stopped at block 7580.

With reference to FIG. 23S, an illustrative method 7590 for controlling a fuel assembly of a nuclear fission reactor is started at block 7600. At block 7610, a casing that surrounds a porous mass of nuclear fuel having a volatile fission product is used. At a block 7620, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7630, a casing is used so as to contain a porous mass of nuclear fuel having a large number of pores to allow at least a portion of the volatile fission products to be released within a predetermined response time of between about one second and about 10,000 seconds. The execution of method 7590 is stopped at block 7640.

With reference to FIG. 23T, an illustrative method 7650 for controlling a fuel assembly of a nuclear fission reactor is started at block 7660. At block 7670, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7680, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7690, a casing is used so as to hermetically accommodate a cylindrical porous mass of nuclear fuel. The execution of method 7650 is stopped at block 7700.

With reference to FIG. 23U, an illustrative method 7710 for controlling a fuel assembly of a nuclear fission reactor is started at block 7720. At block 7730, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7740, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7750, a casing is used so as to hermetically enclose a porous mass of nuclear fuel having a polygonal shape. The execution of method 7710 is stopped at block 7760.

With reference to FIG. 23V, an illustrative method 7770 for controlling a fuel assembly of a nuclear fission reactor is started at block 7780. At block 7790, a casing is used that surrounds a porous mass of nuclear fuel having a volatile fission product. At a block 7800, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor, controlling the flow of fluid in a large the number of regions of a nuclear fission reactor on a traveling wave, near a large number of locations corresponding to a combustion wave. At a block 7810, a casing is used to accommodate a porous mass of nuclear fuel having a large number of pores to produce volatile fission products released by a combustion wave in a traveling wave fission reactor. The execution of method 7770 is stopped at block 7820.

With reference to FIG. 23W, an illustrative method 7830 for controlling a fuel assembly of a nuclear fission reactor is started at block 7840. At block 7850, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7860, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7870, a casing is used so as to accommodate a porous mass of nuclear fuel having a large number of pores for transporting volatile fission products through the porous mass of nuclear fuel. The execution of method 7830 is terminated at block 7880.

With reference to FIG. 23X, an illustrative method 7890 for controlling a fuel assembly of a nuclear fission reactor is started at block 7900. At block 7910, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 7920, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7930, volatile fission products are received in a reservoir coupled to the fluid control subassembly. The execution of method 7890 is stopped at block 7940.

With reference to FIG. 23Y, an illustrative method 7950 for controlling a fuel assembly of a nuclear fission reactor is started at block 7960. At block 7970, a casing is used that surrounds a porous mass of nuclear fuel having a volatile fission product. At a block 7980, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 7990, a fluid control subassembly is used to circulate the nuclear fission product removal fluid through the porous mass of nuclear fuel so that at least a portion of the volatile fission product is removed from the porous mass of nuclear fuel, while the fluid control subassembly circulates the removal product nuclear fission fluid through a porous mass of nuclear fuel. The execution of method 7950 is stopped at block 8000.

With reference to FIG. 23Z, an illustrative method 8010 for controlling a fuel assembly of a nuclear fission reactor is started at block 8020. At block 8030, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8040, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8050, a fluid control subassembly is used to circulate the nuclear fission product removal fluid through the porous mass of nuclear fuel so that at least a portion of the volatile fission product is removed from the porous nuclear fuel mass, while the fluid control subassembly circulates the removal product nuclear fission fluid through a porous mass of nuclear fuel. At a block 8060, a fission product-removing fluid is supplied to the porous mass of nuclear fuel using an inlet subassembly. The execution of method 8010 is stopped at block 8070.

With reference to FIG. 23AA, an illustrative method 8080 for controlling a fuel assembly of a nuclear fission reactor is started at block 8090. At block 8100, a casing that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product is used. At a block 8110, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8120, a fluid control subassembly is used to circulate the nuclear fission product removal fluid through the porous mass of nuclear fuel such that at least a portion of the volatile fission product is removed from the porous mass of the nuclear fuel, while the fluid control subassembly circulates the removal product nuclear fission fluid through a porous mass of nuclear fuel. At a block 8130, a nuclear fission product removal fluid is removed from the porous mass of nuclear fuel using an output subunit. The execution of method 8080 is stopped at block 8140.

With reference to FIG. 23AB, an illustrative method 8150 for controlling a fuel assembly of a nuclear fission reactor is started at block 8160. At block 8170, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8180, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8190, a fluid control subassembly is used to circulate the nuclear fission product removal fluid through the porous mass of nuclear fuel such that at least a portion of the volatile fission product is removed from the porous mass of the nuclear fuel, while the fluid control subassembly circulates the removal product nuclear fission fluid through a porous mass of nuclear fuel. At a block 8200, a nuclear fission product removal fluid is obtained in a reservoir coupled to a fluid control subassembly. The execution of method 8150 is stopped at block 8210.

With reference to FIG. 23AC, an illustrative method 8220 for controlling a fuel assembly of a nuclear fission reactor is started at block 8230. At block 8240, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8250, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8260, a fluid control subassembly is used to circulate the nuclear fission product removal fluid through the porous mass of nuclear fuel so that at least a portion of the volatile fission product is removed from the porous mass of the nuclear fuel, while the fluid control subassembly circulates the removal product nuclear fission fluid through a porous mass of nuclear fuel. At a block 8270, a fission product-removing fluid is supplied from a reservoir connected to the fluid control subassembly. The execution of method 8220 is terminated at block 8280.

With reference to Fig.23AD, an illustrative method 8290 for controlling the fuel assembly of a nuclear fission reactor is started at block 8300. At block 8310, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8320, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8330, a fluid control subassembly is used such that the fuel assembly of the nuclear fission reactor is configured to circulate gas through the pores of the porous mass of nuclear fuel. The execution of method 8290 is stopped at block 8340.

With reference to FIG. 23AE, an illustrative method 8350 for controlling a fuel assembly of a nuclear fission reactor is started at block 8360. At block 8370, a casing that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product is used. At a block 8380, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8390, a fluid control subassembly is used such that a fuel assembly of a nuclear fission reactor is configured to circulate liquid through a porous mass of nuclear fuel. The execution of method 8350 is stopped at block 8400.

With reference to FIG. 23AF, an illustrative method 8410 for controlling a fuel assembly of a nuclear fission reactor is started at block 8420. At block 8430, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8440, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8450, the method includes driving a pump. The execution of method 8410 is stopped at block 8460.

With reference to FIG. 23AG, an illustrative method 8470 for controlling a fuel assembly of a nuclear fission reactor is started at block 8480. At block 8490, a casing that surrounds a porous mass of nuclear fuel having a volatile fission product is used. At a block 8500, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8510, fluid is circulated between the fluid control subassembly and the porous mass of nuclear fuel by driving a pump integrally coupled to the fluid control subassembly. The execution of method 8470 is stopped at block 8520.

With reference to FIG. 23AN, an illustrative method 8530 for controlling a fuel assembly of a nuclear fission reactor is started at block 8540. At block 8550, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8560, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8570, the method includes actuating the valve. The execution of method 8530 is terminated at block 8580.

With reference to FIG. 23AI, an illustrative method 8590 for controlling a fuel assembly of a nuclear fission reactor is started at block 8600. At block 8610, a casing that surrounds a porous mass of nuclear fuel having a volatile fission product is used. At a block 8620, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8630, fluid flow is controlled between the housing and the fluid control assembly of the operating valve located between the housing and the fluid control subassembly. The execution of method 8590 is stopped at block 8640.

With reference to FIG. 23AJ, an illustrative method 8650 for controlling a fuel assembly of a nuclear fission reactor is started at block 8660. At block 8670, a casing that surrounds a porous mass of nuclear fuel having a volatile fission product is used. At a block 8680, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8690, fluid flow is controlled between the casing and the fluid control subassembly by actuating a valve located between the casing and the fluid control subassembly. At a block 8700, fluid flow is controlled between the housing and the fluid control subassembly by actuating a backflow prevention valve. The execution of method 8650 is stopped at block 8710.

With reference to Fig. 23AK, an illustrative method 8720 for controlling a fuel assembly of a nuclear fission reactor is started at block 8730. At block 8740, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8750, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8760, the method includes actuating a barrier configured for controlled destruction. The execution of method 8720 is terminated at block 8770.

With reference to Fig. 23AL, an illustrative method 8780 for controlling a fuel assembly of a nuclear fission reactor is started at block 8790. At block 8800, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8810, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8820, a barrier located between the casing and the fluid control subassembly is used, which is capable of controlled disruption. The execution of method 8780 is stopped at block 8830.

With reference to FIG. 23AM, an illustrative method 8840 for controlling a fuel assembly of a nuclear fission reactor is started at block 8850. At block 8860, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8870, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8880, a barrier located between the casing and the fluid control subassembly is used, which is capable of controlled disruption. At a block 8890, a barrier configured to break at a given pressure is used. The execution of method 8840 is terminated at block 8900.

With reference to FIG. 23AN, an illustrative method 8910 for controlling a fuel assembly of a nuclear fission reactor is started at block 8920. At block 8930, a casing is used that surrounds a porous mass of nuclear fuel having a volatile nuclear fission product. At a block 8940, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel at a large number of locations corresponding to the combustion wave of a traveling fission nuclear fission reactor by controlling the flow of fluid into a large number of regions of a traveling fission nuclear fission reactor, near a large number of locations corresponding to a combustion wave. At a block 8950, a barrier located between the casing and the fluid control subassembly is used, which is capable of controlled disruption. At a block 8960, a barrier is used that is capable of breaking as a result of operator action. The execution of method 8910 is stopped at block 8970.

With reference to FIG. 23AO, an illustrative method 8980 for controlling the fuel assembly of a nuclear fission reactor is started at block 8990. At block 9000, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9010, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the combustion wave traveling wave fission reactor by controlling the flow of fluid in a large number of regions of a traveling wave fission reactor near a large number of locations positions corresponding to the combustion wave. The execution of method 8980 is stopped at block 9020.

With reference to FIG. 23AP, an illustrative method 9030 for controlling a fuel assembly of a nuclear fission reactor is started at block 9040. At block 9050, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9060, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9070, the operation of the fluid control subassembly is controlled by controlling a control unit connected to the fluid control subassembly. The execution of method 9030 is terminated at block 9080.

With reference to FIG. 23AQ, an exemplary method 9090 for controlling a fuel assembly of a nuclear fission reactor is started at block 9100. At block 9110, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9120, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9130, the casing is used to accommodate a mass of nuclear fuel. The execution of method 9090 is terminated at block 9140.

With reference to FIG. 23AR, an illustrative method 9150 for controlling a fuel assembly of a nuclear fission reactor is started at block 9160. At block 9170, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9180, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores from the mass of nuclear fuel, and to control the removal of at least a portion of the heat generated by the mass of nuclear fuel at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9190, a casing is used so as to accommodate fissile material forming a mass of nuclear fuel. The execution of method 9150 is stopped at block 9200.

With reference to FIG. 23AS, an illustrative method 9210 for controlling a fuel assembly of a nuclear fission reactor is started at block 9220. At block 9230, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9240, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores from the mass of nuclear fuel, and to control the removal of at least a portion of the heat generated by the mass of nuclear fuel at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9250, a casing is used so as to accommodate a reproducing material forming a mass of nuclear fuel. The execution of method 9210 is terminated at block 9260.

With reference to FIG. 23AT, an illustrative method 9270 for controlling a fuel assembly of a nuclear fission reactor is started at block 9280. At block 9290, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9300, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9310, a casing is used so as to accommodate a mixture of fissile and reproducing material forming a mass of nuclear fuel. The execution of method 9270 is stopped at block 9320.

With reference to FIG. 23AU, an illustrative method 9330 for controlling a fuel assembly of a nuclear fission reactor is started at block 9340. At block 9350, a casing is used that accommodates a heat-generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9360, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave combustion of a nuclear fission reactor on a traveling wave, controlling the flow of fluid in a large number of regions of a nuclear fission reactor on a traveling wave, near a large number of corresponding to the combustion wave. At a block 9370, a fluid control subassembly is used to enable controlled release of volatile fission products in response to the position of the combustion wave in the traveling wave fission reactor. The execution of method 9330 is stopped at block 9380.

With reference to FIG. 23AV, an illustrative method 9390 for controlling a fuel assembly of a nuclear fission reactor is started at block 9400. At block 9410, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9420, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave combustion of a nuclear fission reactor on a traveling wave, controlling the flow of fluid in a large number of regions of a nuclear fission reactor on a traveling wave, near a large number of locations th corresponding to the combustion wave. At a block 9430, a fluid control subassembly is used to enable controlled release of volatile fission products in response to a power level in a traveling wave fission reactor. The execution of method 9390 is stopped at block 9440.

With reference to FIG. 23AW, an illustrative method 9450 for controlling a fuel assembly of a nuclear fission reactor is started at block 9460. At block 9470, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9480, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave combustion of a nuclear fission reactor on a traveling wave, controlling the flow of fluid in a large number of regions of a nuclear fission reactor on a traveling wave, near a large number of locations th corresponding to the combustion wave. At a block 9490, a fluid control subassembly is used to provide controlled release of volatile fission products in response to a neutron population level in a traveling wave fission reactor. The execution of method 9450 is terminated at block 9500.

With reference to FIG. 23AX, an illustrative method 9510 for controlling a fuel assembly of a nuclear fission reactor is started at block 9520. At block 9530, a casing is used that accommodates a heat-generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9540, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9550, a fluid control subassembly is used to provide controlled release of volatile fission products in response to pressure of volatile fission products in a traveling wave nuclear fission reactor. The execution of method 9510 is stopped at block 9560.

With reference to FIG. 23AY, an illustrative method 9570 for controlling the fuel assembly of a nuclear fission reactor is started at block 9580. At block 9590, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9600, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large 'number of locations corresponding to the wave of combustion of a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places positions corresponding to the combustion wave. At a block 9610, a fluid control subassembly is used to enable controlled release of volatile fission products in response to a timeline associated with a traveling wave nuclear fission reactor. The execution of method 9570 is stopped at block 9620.

With reference to FIG. 23AZ, an illustrative method 9630 for controlling a fuel assembly of a nuclear fission reactor is started at block 9640. At block 9650, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9660, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9670, a fluid control subassembly is used to provide controlled release of volatile fission products in response to the amount of time that the traveling wave nuclear fission reactor is operating. The execution of method 9630 is terminated at block 9680.

With reference to FIG. 23BA, an illustrative method 9690 for controlling a fuel assembly of a nuclear fission reactor is started at block 9700. At block 9710, a casing is used that accommodates a heat-generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9720, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9730, volatile fission products are obtained in a reservoir coupled to a fluid control subassembly. The execution of method 9690 is terminated at block 9740.

With reference to FIG. 23BB, an illustrative method 9750 for controlling a fuel assembly of a nuclear fission reactor is started at block 9760. At block 9770, a casing is used that accommodates a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9780, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9790, a fluid control subassembly is used to circulate the nuclear fission product removal fluid through the pores of the nuclear fuel mass, so that at least a portion of the volatile nuclear fission product is removed from the pores of the nuclear fuel mass, while the fluid control subunit circulates the nuclear fission product removal fluid through the pores of the mass of nuclear fuel. The execution of method 9750 is stopped at block 9800.

With reference to FIG. 23BC, an illustrative method 9810 for controlling the fuel assembly of a nuclear fission reactor is started at block 9820. At block 9830, a casing is used that accommodates a heat-generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9840, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 9850, a fluid control subassembly is used such that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removal fluid, the method including supplying a nuclear fission product removal fluid to the pores of a nuclear fuel mass using an input subassembly. The execution of method 9810 is stopped at block 9860.

With reference to FIG. 23BD, an illustrative method 9870 for controlling a fuel assembly of a nuclear fission reactor is started at block 9880. At block 9890, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 9900, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the combustion wave traveling wave fission reactor by controlling the flow of fluid in a large number of regions of a traveling wave fission reactor near a large number of locations positions corresponding to the combustion wave. At a block 9910, a fluid control subassembly is used such that a fuel assembly of a nuclear fission reactor is configured to circulate a nuclear fission product removal fluid, the method including removing the nuclear fission product removal fluid from the pores of the nuclear fuel mass using an output subassembly. The execution of method 9870 is stopped at block 9920.

With reference to FIG. 23BE, an exemplary method 9930 for controlling the fuel assembly of a nuclear fission reactor is started at block 9940. At block 9950, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 9960, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the combustion wave traveling wave fission reactor by controlling the flow of fluid in a large number of regions of a traveling wave fission reactor near a large number of locations positions corresponding to the combustion wave. At a block 9970, the fluid control subassembly is used such that the fuel assembly of the nuclear fission reactor is configured to circulate heat dissipating fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat generated by the nuclear fuel mass is removed from the nuclear fuel mass, then as a fluid control subunit, heat-dissipating fluid circulates through the pores of a mass of nuclear fuel. The execution of method 9930 is terminated at block 9980.

With reference to FIG. 23BP, an illustrative method 9990 for controlling a fuel assembly of a nuclear fission reactor is started at block 10000. At block 10010, a casing is used that holds a heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10020, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the combustion wave a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places Assumption corresponding combustion wave. At a block 10030, a fluid control subassembly is used such that the fuel assembly of the nuclear fission reactor is configured to circulate heat-dissipating fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat generated by the nuclear fuel mass is removed from the nuclear fuel mass, then as a fluid control subunit, heat-dissipating fluid circulates through the pores of a mass of nuclear fuel. At a block 10040, heat-dissipating fluid enters a reservoir connected to the fluid control subassembly. The execution of method 9990 is stopped at block 10050.

With reference to FIG. 23BC, an illustrative method 10060 for controlling a fuel assembly of a nuclear fission reactor is started at block 10070. At block 10080, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10090, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10100, the fluid control subassembly is used such that the fuel assembly of the nuclear fission reactor is configured to circulate heat-removing fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat generated by the nuclear fuel mass is removed from the nuclear fuel mass, then as a fluid control subunit, heat-dissipating fluid circulates through the pores of a mass of nuclear fuel. At a block 10110, heat dissipating fluid is supplied from a reservoir connected to the fluid control subassembly. The execution of method 10060 is stopped at block 10120.

With reference to FIG. 23BH, an illustrative method 10130 for controlling the fuel assembly of a nuclear fission reactor is started at block 10140. At block 10150, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10160, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10170, the fluid control subassembly is used such that the fuel assembly of the nuclear fission reactor is configured to circulate heat-dissipating fluid through the pores of the mass of nuclear fuel, so that at least a portion of the heat generated by the mass of nuclear fuel is removed from the mass of nuclear fuel, then as a fluid control subunit, heat-dissipating fluid circulates through the pores of a mass of nuclear fuel. At a block 10180, heat is removed from the heat-dissipating fluid using a radiator connected to the fluid control subassembly, so that the radiator is in communication through heat transfer to the heat-discharging fluid. The execution of method 10130 is stopped at block 10190.

With reference to FIG. 23BI, an illustrative method 10200 for controlling a fuel assembly of a nuclear fission reactor is started at block 10210. At block 10220, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10230, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10240, a fluid control subassembly is used such that the fuel assembly of the nuclear fission reactor is configured to circulate heat-dissipating fluid through the pores of the nuclear fuel mass, so that at least a portion of the heat generated by the nuclear fuel mass is removed from the nuclear fuel mass, then as a fluid control subunit, heat-dissipating fluid circulates through the pores of a mass of nuclear fuel. At a block 10250, heat is removed from the heat-dissipating fluid using a heat exchanger connected to the fluid control subassembly, so that the heat exchanger is in communication through heat transfer to the heat-discharging fluid. The execution of method 10200 is terminated at block 10260.

With reference to FIG. 23BJ, an illustrative method 10270 for controlling a fuel assembly of a nuclear fission reactor is started at block 10280. At block 10290, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10300, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10310, a fluid control subassembly is used to simultaneously circulate a fission product-removing fluid and heat-removing fluid. The execution of method 10270 is stopped at block 10311.

With reference to FIG. 23BK, an illustrative method 10312 for controlling a fuel assembly of a nuclear fission reactor is started in block 10313. At block 10314, a casing is used that accommodates a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10315, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile nuclear fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave of combustion of a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places positions corresponding to the combustion wave. At a block 10316, a fluid control subassembly is used to sequentially circulate a fluid fission product and heat removal fluid. The execution of method 10312 is stopped at block 10317.

With reference to FIG. 23BL, an illustrative method 10318 for controlling a fuel assembly of a nuclear fission reactor is started at block 10319. At block 10320, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10330, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10340, the method includes driving a pump. The execution of method 10318 is stopped at block 10350.

With reference to FIG. 23BM, an illustrative method 10360 for controlling a fuel assembly of a nuclear fission reactor is started at block 10370. At block 10380, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10390, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10400, fluid is pumped between the fluid control subassembly and the pores of the mass of nuclear fuel by driving a pump integrally coupled to the fluid control subassembly. The execution of method 10360 is stopped at block 10410.

With reference to FIG. 23BN, an illustrative method 10420 for controlling the fuel assembly of a nuclear fission reactor is started at block 10430. At block 10440, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10450, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10460, a large number of first elements coupled to the fluid control subassembly are used to supply the nuclear fission product removal fluid to the fluid control subassembly so as to allow the fluid control subassembly to circulate the nuclear fission product removal fluid through the pores of the nuclear mass fuel, whereby at least a portion of the volatile fission products enters the pores of the mass of nuclear fuel and is removed from the pores of the mass of nuclear fuel, while I, as a fluid control subassembly, circulates a fluid that removes nuclear fission products through the pores of a mass of nuclear fuel. The execution of method 10420 is terminated at block 10470.

With reference to FIG. 23BO, an illustrative method 10480 for controlling the fuel assembly of a nuclear fission reactor is started at block 10490. At block 10500, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10510, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10520, a large number of first elements coupled to the fluid control subassembly are used to supply the nuclear fission product removal fluid to the fluid control subassembly so as to allow the fluid control subassembly to circulate the nuclear fission product removal fluid through the pores of the nuclear mass fuel, whereby at least a portion of the volatile fission products enters the pores of the mass of nuclear fuel and is removed from the pores of the mass of nuclear fuel, while I, as a fluid control subassembly, circulates a fluid that removes nuclear fission products through the pores of a mass of nuclear fuel. At a block 10530, a large number of second elements coupled to the fluid control subassembly are used to supply heat dissipating fluid to the fluid control subassembly so as to allow the fluid control subassembly to circulate the heat dissipating fluid through the pores of the nuclear fuel mass, resulting in whereby at least a portion of the heat generated by the mass of nuclear fuel is removed from the mass of nuclear fuel, while the fluid control subunit circulates the heat-dissipating fluid from food through the pores of the nuclear fuel supply. The execution of method 10480 is terminated at block 10540.

With reference to FIG. 23BP, an illustrative method 10550 for controlling the fuel assembly of a nuclear fission reactor is started at block 10560. At block 10570, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10580, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10590, a large number of first elements coupled to the fluid control subassembly are used to supply the nuclear fission product removal fluid to the fluid control subassembly so as to allow the fluid control subassembly to circulate the nuclear fission product removal through the pores of the nuclear mass fuel, whereby at least a portion of the volatile fission products enters the pores of the mass of nuclear fuel and is removed from the pores of the mass of nuclear fuel, while I, as the indicated fluid control subassembly, circulates a fluid that removes nuclear fission products through the pores of the mass of nuclear fuel. At a block 10600, a large number of second elements coupled to the fluid control subassembly are used to supply heat dissipating fluid to the fluid control subassembly so as to allow the fluid control subassembly to circulate the heat discharging fluid through the pores of the nuclear fuel mass, resulting in whereby at least a portion of the heat generated by the mass of nuclear fuel is removed from the mass of nuclear fuel, while the fluid control subunit circulates the heat-dissipating fluid from food through the pores of the nuclear fuel supply. At a block 10610, the first elements and second elements are used so that at least one of the first elements and at least one of the second elements are identical. The execution of method 10550 is stopped at block 10620.

With reference to FIG. 23BQ, an illustrative method 10630 for controlling the fuel assembly of a nuclear fission reactor is started at block 10640. At block 10650, a casing is used that accommodates a heat generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10660, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10670, a dual-use loop connected to the casing is used to selectively remove volatile fission products and heat from the mass of nuclear fuel. The execution of method 10630 is terminated at block 10680.

With reference to FIG. 23BR, an illustrative method 10690 for controlling a fuel assembly of a nuclear fission reactor is started at block 10700. At block 10710, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10720, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10730, a fluid control subassembly is used to circulate gas through the pores of the mass of nuclear fuel. The execution of method 10690 is terminated at block 10740.

With reference to FIG. 23BS, an illustrative method 10750 for controlling a fuel assembly of a nuclear fission reactor is started at block 10760. At block 10770, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10780, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10790, a fluid control subassembly is used to circulate fluid through the pores of the mass of nuclear fuel. The execution of method 10750 is stopped at block 10800.

With reference to FIG. 23BT, an illustrative method 10810 for controlling a fuel assembly of a nuclear fission reactor is started at block 10820. At block 10830, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10840, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10850, a casing is used in such a manner as to accommodate a mass of nuclear fuel made in the form of foam material restricting a large number of pores. The execution of method 10810 is terminated at block 10860.

With reference to FIG. 23BU, an illustrative method 10870 for controlling a fuel assembly of a nuclear fission reactor is started at block 10880. At block 10890, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 10900, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10910, a casing is used so as to accommodate a mass of nuclear fuel having a large number of channels. The execution of method 10870 is stopped at block 10920.

With reference to FIG. 23BV, an illustrative method 10930 for controlling a fuel assembly of a nuclear fission reactor is started at block 10940. At block 10950, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 10960, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 10970, a casing is used so as to accommodate a mass of nuclear fuel having a large number of channels. At a block 10980, a casing is used so as to accommodate a mass of nuclear fuel having a large number of particles restricting a large number of channels between them. The execution of method 10930 is terminated at block 10990.

With reference to FIG. 23BW, an illustrative method 11000 for controlling a fuel assembly of a nuclear fission reactor is started at block 11010. At block 11020, a casing is used that accommodates a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11030, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11040, a casing is used so as to accommodate a mass of nuclear fuel that limits a large number of pores, with a large number of pores having a spatially inhomogeneous distribution. The execution of method 11000 is stopped at block 11050.

With reference to FIG. 23BX, an illustrative method 11060 for controlling a fuel assembly of a nuclear fission reactor is started at block 11070. At block 11080, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11090, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11100, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores to produce volatile fission products released by a combustion wave in a traveling wave fission reactor. The execution of method 11060 is stopped at block 11110.

With reference to FIG. 23BY, an illustrative method 11120 for controlling a fuel assembly of a nuclear fission reactor is started at block 11130. At block 11140, a casing is used that accommodates a heat generating mass of nuclear fuel, wherein the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11150, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11160, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores, wherein one or more of the large number of pores have a predetermined configuration to allow at least a portion of the volatile fission products to be released from the mass of nuclear fuel into for a predetermined response time. The execution of method 11120 is terminated at block 11170.

With reference to FIG. 23BZ, an illustrative method 11180 for controlling a fuel assembly of a nuclear fission reactor is started at block 11190. At block 11200, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 11210, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11220, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores so as to enable at least a portion of the volatile fission products to be released from the nuclear fuel mass within a predetermined response time of between about 10 seconds and about 1000 seconds. The execution of method 11180 is terminated at block 11230.

With reference to FIG. 23CA, an illustrative method 11240 for controlling a fuel assembly of a nuclear fission reactor is started at block 11250. At block 11260, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 11270, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11280, a casing is used so as to contain a mass of nuclear fuel having a large number of pores so as to allow at least a portion of the volatile fission products to be released from the nuclear fuel mass within a predetermined response time of between about one second and about 10,000 seconds . The execution of method 11240 is terminated at block 11290.

With reference to FIG. 23CB, an illustrative method 11300 for controlling the fuel assembly of a nuclear fission reactor is started at block 11310. At block 11320, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11330, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores from the mass of nuclear fuel and to control the removal of at least a portion of the heat the mass of nuclear fuel at a large number of locations corresponding to the combustion wave of the nuclear reactor fission on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear reactor fission on a traveling wave, near a large number of locations, respectively favoring the combustion wave. At a block 11340, a casing is used so as to accommodate a mass of nuclear fuel having a large number of pores for transferring volatile fission products through the mass of nuclear fuel. The execution of method 11300 is stopped at block 11350.

With reference to FIG. 23CC, an illustrative method 11360 for controlling a fuel assembly of a nuclear fission reactor is started at block 11370. At block 11380, a casing is used that accommodates a heat-generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 11390, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11400, a casing is used so as to hermetically accommodate a cylindrical mass of nuclear fuel. The execution of method 11360 is stopped at block 11410.

With reference to FIG. 23CD, an illustrative method 11420 for controlling a fuel assembly of a nuclear fission reactor is started at block 11430. At block 11440, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 11450, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11460, a casing is used so as to hermetically accommodate a polygonal mass of nuclear fuel. The execution of method 11420 is terminated at block 11470.

With reference to FIG. 23CE, an illustrative method 11480 for controlling a fuel assembly of a nuclear fission reactor is started at block 11490. At block 11500, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11510, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11520, the method includes actuating the valve. The execution of method 11480 is stopped at block 11530.

With reference to FIG. 23CF, an illustrative method 11540 for controlling a fuel assembly of a nuclear fission reactor is started at block 11550. At block 11560, a casing is used that accommodates a heat generating mass of nuclear fuel, wherein the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11570, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11580, fluid flow is controlled between the casing and the fluid control subassembly by actuating a valve located between the casing and the fluid control subassembly. The execution of method 11540 is terminated at block 11590.

With reference to FIG. 23CG, an illustrative method 11600 for controlling a fuel assembly of a nuclear fission reactor is started at block 11610. At block 11620, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 11630, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11640, fluid flow is controlled between the casing and the fluid control subassembly by actuating a valve located between the casing and the fluid control subassembly. At a block 11650, fluid flow is controlled between the casing and the fluid control subassembly by actuating a backflow preventer. The execution of method 11600 is terminated at block 11660.

With reference to FIG. 23CH, an illustrative method 11670 for controlling a fuel assembly of a nuclear fission reactor is started at block 11680. At block 11690, a casing is used that accommodates a heat generating mass of nuclear fuel, the mass of nuclear fuel restricting a large number of interconnected pores with open cells. At a block 11700, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11710, a barrier is used that is capable of controlled destruction. The execution of method 11670 is terminated at block 11720.

With reference to FIG. 23CI, an illustrative method for controlling a fuel assembly of a nuclear fission reactor starts at block 11740. At block 11750, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11760, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11770, a barrier capable of controlled disruption is placed between the casing and the fluid control subassembly. The execution of method 11730 is terminated at block 11780.

With reference to FIG. 23CJ, an illustrative method 11790 for controlling the fuel assembly of a nuclear fission reactor is started at block 11800. At block 11810, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11820, a fluid control subassembly connected to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass, and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11830, a barrier capable of controlled destruction is placed between the housing and the fluid control subassembly. The execution of method 11790 is terminated at block 11840.

With reference to FIG. 23CS, an illustrative method 11850 for controlling the fuel assembly of a nuclear fission reactor is started at block 11860. At block 11870, a casing is used that holds a heat-generating mass of nuclear fuel, and the mass of nuclear fuel limits a large number of interconnected pores with open cells. At a block 11880, a fluid control subassembly coupled to the casing is used to control the removal of at least a portion of the volatile fission products from the pores of the nuclear fuel mass and to control the removal of at least a portion of the heat generated by the nuclear fuel mass at a large number of locations corresponding to the wave burning a nuclear fission reactor on a traveling wave, by controlling the flow of fluid in a large number of areas of a nuclear fission reactor on a traveling wave, near a large number of places provisions corresponding to the combustion wave. At a block 11890, a barrier is arranged to be broken by an operator. The execution of method 11850 is terminated at block 11900.

One skilled in the art will understand that the elements described here (for example, operations), devices, objects, and the accompanying discussions are used only as examples for conceptual clarity, and that various configuration modifications are contemplated. Therefore, in this description, specific examples and accompanying discussions are set forth to represent more general classes. In general, the use of any particular instance is intended to represent its class, and also not to include individual elements (for example, operations), devices and objects should not be construed as limiting.

In addition, it will be understood by those skilled in the art that the above specific illustrative processes and / or devices and / or technologies are representative of the more general processes and / or devices and / or technologies described herein, for example, in the claims filed with this application , and / or in other parts of the present description.

Although individual embodiments of the disclosed subject matter have been shown and described above, those skilled in the art should understand that, based on the inventive ideas presented herein, changes and modifications can be made without departing from the subject matter described here and more broad aspects and, therefore, the appended claims encompasses within its scope all such changes and modifications that are consistent within essentially ti and scope of the subject invention described herein. Professionals should keep in mind that, in general, the terms used in this document, and especially in the claims (for example, in the appended claims), are generally intended to be “open” features (for example, the term “including” should interpreted as “including, but not limited to,” the term “having” should be interpreted as “having at least”, the term “comprising” should be interpreted as “containing, but not limited to,” etc.). Professionals should also understand that if a specific number of transfers of the claimed properties are intended, such an intention will be explicitly realized in the claims, and in the absence of such a transfer, such a goal is not pursued. For example, as an aid to understanding the foregoing, the following appended claims may include the use of the introductory phrases “at least one” and “one or more” to introduce a listing requirement. However, the use of such phrases should not be construed as suggesting that the introduction of the enumeration of the claimed properties by using the indefinite articles "a" or "an", limiting any specific claim that contains such a listing of the claimed properties, clause which contains only one such listing, even when the same paragraph contains the introductory phrases “one or more” or “at least one” and indefinite articles such as “a” or “an” (for example, “a” and / or "an" like pr rule, should be interpreted to mean "at least one" or "one or more"); the same applies to the use of certain articles used to list the claimed properties. In addition, even if a certain number of introduced enumerations of the claimed properties is obvious, it will be clear to specialists in this field that such an enumeration should, as a rule, be construed as at least the enumerated amount (for example, a simple enumeration of “two enumerations”, without other modifiers as a rule, means at least two transfers, or two or more transfers). In addition, in cases where a rule similar to “at least one of A, B and C, etc.” is used, the whole design is intended in the sense that one skilled in the art will understand the rule (for example, “ a system having at least one of A, B and C "will include, but is not limited to systems that have only one A, one B, one C, A and B together, A and C together, B and C together and / or A, B and C together, etc.). In cases where a rule similar to “at least one of A, B or C, etc.” is used, the whole design is intended in the sense that one skilled in the art will understand the rule (for example, “system, having at least one of A, B or C "will include, but is not limited to systems that have one A, one B, one C, A and B together, A and C together, B and C together and / or A, B and C together, etc.). The person skilled in the art will also understand that usually a disjunctive word and / or phrase representing two or more alternative terms, whether in the description of the invention, claims or in the drawings, should be understood as providing the possibility of including one of the terms, any of the terms, or both terms, unless the context dictates otherwise. For example, the phrase “A or B” will usually be understood as the possibilities of “A” or “B”, or “A” and “B”.

As for the claims, those skilled in the art should understand that the operations described in the claims as a whole can be performed in any order. In addition, despite the fact that different operating flows are presented in sequence (s), it should be understood that various operations can be performed in different orders than those orders shown in the drawings, or they can be performed simultaneously. Examples of such alternative orders may include overlapping, interleaving, interrupting, rearranging, incrementing, preparing, complementing, simultaneous, reversing, or another ordering option, unless the context dictates otherwise. In addition, terms such as “configured to respond to,” “associated with,” or other past tense adjectives are generally not intended to exclude the possibility of such an option, unless the context dictates otherwise.

Although various embodiments and aspects have been described herein, other embodiments and aspects will be apparent to those skilled in the art. For example, each of the embodiments of the fuel assembly of a nuclear fission reactor can be located in a thermal neutron reactor, in a fast neutron reactor, in a neutron multiplier reactor or in a fast neutron multiplier reactor. Thus, each of the options for the fuel assembly is versatile enough to be advantageously used in various designs of a nuclear reactor.

Therefore, a fuel assembly of a nuclear fission reactor and a system configured to control the removal of volatile fission products and heat generated by a combustion wave in a traveling wave nuclear fission reactor, as well as a method associated with them, are provided.

Moreover, the various embodiments and aspects described herein are intended for illustrative purposes only and are not intended to be limiting, and the true scope and spirit of the invention is determined by the following claims.

Claims (36)

1. A fuel assembly of a nuclear fission reactor configured to control the removal of volatile fission products released by a combustion wave in a traveling wave nuclear fission reactor, comprising:
a casing configured to accommodate the porous mass of nuclear fuel,
a fluid control subassembly connected to said casing and configured to control the removal of at least a portion of the volatile fission products from the porous mass of nuclear fuel; and
a valve located between the casing and the specified fluid control subassembly and designed to control the fluid flow between them;
wherein said valve comprises a backflow prevention valve. 2. The fuel assembly of the nuclear fission reactor according to claim 1, further comprising a control unit configured to control the operation of said fluid control subassembly. 3. The fuel assembly of a nuclear fission reactor according to claim 2, wherein the control unit is configured to provide controlled release of volatile fission products in response to a power level in a traveling wave fission reactor. 4. The fuel assembly of the nuclear fission reactor according to claim 2, wherein the control unit is configured to provide controlled release of volatile fission products in response to a neutron population level in the traveling wave fission reactor. 5. The fuel assembly of the nuclear fission reactor according to claim 2, wherein the control unit is configured to provide controlled release of volatile fission products in response to pressure of the volatile fission products in the traveling wave nuclear fission reactor. 6. The fuel assembly of the nuclear fission reactor according to claim 2, wherein the control unit is configured to provide controlled release of volatile nuclear fission products in response to a timeline associated with the traveling wave nuclear fission reactor. 7. The fuel assembly of the nuclear fission reactor according to claim 2, in which the control unit is configured to provide controlled release of volatile fission products in response to the amount of time that the running fission nuclear fission reactor operates. 8. The fuel assembly of the nuclear fission reactor according to claim 1, wherein the fluid control subassembly is configured to provide controlled release of volatile fission products in response to the position of the combustion wave in the traveling wave fission reactor. 9. The fuel assembly of the nuclear fission reactor according to claim 1, in which the casing contains a porous mass of nuclear fuel. 10. The fuel assembly of a nuclear fission reactor according to claim 1, in which the casing is configured to receive fissile material forming a porous mass of nuclear fuel. 11. The fuel assembly of a nuclear fission reactor according to claim 1, in which the casing is configured to accommodate a reproducing material forming a porous mass of nuclear fuel. 12. The fuel assembly of the nuclear fission reactor according to claim 1, wherein the casing is configured to receive a mixture of fissile and reproducing material forming a porous mass of nuclear fuel. 13. The fuel assembly of a nuclear fission reactor according to claim 1, in which the casing is configured to accommodate a porous mass of nuclear fuel, limiting a large number of channels. 14. The fuel assembly of the nuclear fission reactor according to item 13, in which the casing is configured to accommodate the porous mass of nuclear fuel with a large number of particles, limiting a large number of channels between them. 15. The fuel assembly of a nuclear fission reactor according to claim 1, in which the casing is configured to receive a porous mass of nuclear fuel having a large number of pores, and at least some of the large number of pores have a predetermined configuration to enable the release of at least part of the volatile nuclear fission products from the pores of the mass of nuclear fuel for a given response time. 16. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the casing is configured to receive a porous mass of nuclear fuel having a large number of pores to enable the release of at least a portion of the volatile fission products within a predetermined response time of between about 10 seconds and about 1000 seconds. 17. The fuel assembly of the nuclear fission reactor according to claim 1, in which the casing is configured to receive a porous mass of nuclear fuel having a large number of pores to enable the release of at least a portion of the volatile fission products within a predetermined response time of between approximately one second and about 10,000 seconds. 18. The fuel assembly of the nuclear fission reactor according to claim 1, in which the casing is made with the possibility of tight containment of the porous mass of nuclear fuel having a cylindrical shape. 19. The fuel assembly of the nuclear fission reactor according to claim 1, in which the casing is made with the possibility of tight containment of the porous mass of nuclear fuel having a polygonal shape. 20. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the casing is configured to receive a porous mass of nuclear fuel having a large number of pores for producing volatile nuclear fission products released by a combustion wave in a traveling wave fission reactor. 21. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the casing is configured to receive a porous mass of nuclear fuel having a large number of pores for transferring volatile fission products through the porous mass of nuclear fuel. 22. The fuel assembly of a nuclear fission reactor according to claim 1, further comprising a reservoir connected to said fluid control subassembly and for receiving volatile fission products. 23. The fuel assembly of the nuclear fission reactor according to claim 1, wherein the fluid control subassembly is configured to circulate the nuclear fission product removing fluid through the porous mass of nuclear fuel, whereby at least a portion of the volatile nuclear fission products is removed from the porous nuclear mass fuel, while said fluid control subassembly circulates a fission product-removing fluid through a porous mass of nuclear fuel. 24. The fuel assembly of the nuclear fission reactor according to claim 23, wherein the fluid control subassembly comprises an inlet subassembly for supplying a nuclear fission removal fluid to the porous mass of nuclear fuel. 25. The fuel assembly of a nuclear fission reactor according to claim 23, wherein the fluid control subassembly comprises an output subassembly for removing the nuclear fission product removing fluid from the porous mass of nuclear fuel. 26. The fuel assembly of a nuclear fission reactor according to claim 23, further comprising a reservoir connected to said fluid control subassembly and adapted to receive a nuclear fission product removing fluid. 27. The fuel assembly of the nuclear fission reactor according to claim 23, further comprising a reservoir connected to said fluid control subassembly and for supplying a nuclear fission removal product fluid. 28. The fuel assembly of the nuclear fission reactor according to claim 1, in which the porous mass of nuclear fuel limits a large number of pores, wherein said fluid control subassembly is configured to circulate gas through the pores of the porous mass of nuclear fuel. 29. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the porous mass of nuclear fuel limits a large number of pores, wherein said fluid control subassembly is configured to circulate fluid through the pores of the porous mass of nuclear fuel. 30. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the fluid control subassembly comprises a pump. 31. The fuel assembly of the nuclear fission reactor according to claim 1, further comprising a pump integrally coupled to said fluid control subassembly for pumping fluid from the fluid control subassembly to the porous mass of nuclear fuel. 32. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the fluid control subassembly comprises a valve. 33. The fuel assembly of a nuclear fission reactor according to claim 1, wherein the fluid control subassembly comprises a barrier configured to controllably destroy. 34. The fuel assembly of a nuclear fission reactor according to claim 33, wherein said barrier is destroyed at a predetermined pressure. 35. The fuel assembly of a nuclear fission reactor according to claim 33, wherein said barrier is destroyed as a result of the operator. 36. The fuel assembly of a nuclear fission reactor according to claim 1, further comprising a barrier configured for controlled destruction and located between the casing and the fluid control subassembly.

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