KR101986381B1 - Methods and systems for migrating fuel assemblies in a nuclear fission reactor - Google Patents

Abstract

The illustrated embodiment includes a method and system for moving fuel assemblies in a fission reactor, a method of operating a nuclear fission traveling wave reactor, a control method of a fission traveling wave reactor, a control system of a fission traveling wave reactor, a computer software program product for controlling a fission traveling wave reactor, And a system for moving the fuel assembly.

Description

[0001] METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR [0002]

The present invention relates to a method and system for transferring fuel assemblies from fission reactors.

Cross-reference to related application

This application is related to the applications listed below ("Related Applications") and claims the benefit of the earliest available filing date of the applications (eg, parent application of the related application, grand jury application, Claiming the earliest available priority date for an application other than a patent application, or claiming benefit under 35 USC §119 (e) for a patent application, for any application or all applications such as a grandmother application) . All subject matter, including any priority claim, any or all of the parent application, the grandmother application, the grandmother application, etc. of the relevant application and related application, is incorporated herein by reference unless the subject matter is contradictory herein .

Related application

For the purposes of the requirements of the USPTO Special Act, this application is incorporated by reference into the present application by Hugh Green Span, Roderick A. Hyde, Mr. Robert. Petroski, Mr. Joshua. Walter, Thomas Allan Weber, Charles Whitmer, Lowell El. Wood Junior, and George Rain. US patent application Ser. No. 12 / 590,448 filed November 6, 2009 entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR " Shall constitute part of the continuation application. The US application is currently copending, or the present simultaneous continuation application is a filing that has the benefit of the filing date.

For the purposes of the requirements of the USPTO Special Act, this application is incorporated by reference into the present application by Hugh Green Span, Roderick A. Hyde, Mr. Robert. Petroski, Mr. Joshua. Walter, Thomas Allan Weber, Charles Whitmer, Lowell El. Wood Junior, and George Rain. US Patent Application No. 12 / 657,725 filed on January 25, 2010 entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR " Shall constitute part of the continuation application. The above US application is currently concurrently in progress, or the current simultaneous continuation application is an application that takes the benefit of the filing date.

For the purposes of the requirements of the USPTO Special Act, this application is incorporated by reference into the present application by Hugh Green Span, Roderick A. Hyde, Mr. Robert. Petroski, Mr. Joshua. Walter, Thomas Allan Weber, Charles Whitmer, Lowell El. Wood Junior, and George Rain. Filed on January 25, 2010, entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR, " Shall constitute part of the continuation application. The above US application is currently concurrently in progress, or the current simultaneous continuation application is an application that takes the benefit of the filing date.

For the purposes of the requirements of the USPTO Special Act, this application is incorporated by reference into the present application by Hugh Green Span, Roderick A. Hyde, Mr. Robert. Petroski, Mr. Joshua. Walter, Thomas Allan Weber, Charles Whitmer, Lowell El. Wood Junior, and George Rain. US Patent Application No. 12 / 657,735, entitled " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR, " filed January 25, 2010, Shall constitute part of the continuation application. The above US application is currently concurrently in progress, or the current simultaneous continuation application is an application that takes the benefit of the filing date.

The United States Patent and Trademark Office (USPTO) issued a notice that the USPTO's computer program required that the patent applicant cite the serial number of the parent application and indicate whether the application was a continuation of the parent application, Respectively. Stephanie. The 'benefit of the earlier application' written by Kunin in the March 18, 2003, USPTO Gazette. The applicant entity of the present application (hereinafter referred to as the "applicant") provides a specific reference to an application for which priority is claimed as provided for in the statute. Applicant understands that the statute is clear in its specific reference language and does not require a serial number or any characterization, such as "continuing" or "continuing" to claim priority to a US patent application. Notwithstanding this, the Applicant understands that the computer program of the USPTO requires specific data entry requirements, so that the applicant has provided the assignment of the relationship between the present application and its parent application as described above, Clearly point out that the application must not be interpreted in any way as an interpretation and / or an acceptance of whether or not it contains any new matter in addition to the matter of that application.

The illustrated embodiment includes a method and system for moving fuel assemblies in a fission reactor, a method of operating a nuclear fission traveling wave reactor, a control method of a fission traveling wave reactor, a control system of a fission traveling wave reactor, a computer software program product for controlling a fission traveling wave reactor, And a system for moving the fuel assembly.

The above summary is by way of example only and is not intended to be limiting in any manner. In addition to the exemplary aspects, embodiments and features described above, additional aspects, embodiments and features will become apparent by reference to the accompanying drawings and the following detailed description.

Methods and systems for moving fuel assemblies from fission reactors, methods of operating nuclear fission traveling wave reactors, control methods of fission traveling wave reactors, control systems for fission traveling wave reactors, computer software program products for controlling fission traveling wave reactors, A fission-progressive-wave reactor with a system for delivering a nuclear fuel.

Figure 1A is a block diagram illustrating an exemplary method of operating a fission progressive wave reactor.
Figures 1B-D are perspective views partially illustrating a schematic representation of the components of an exemplary fission reactor core.
Figs. 1E to 1H are views showing effects of the shape of the surface of the fission propagation flame generated by the movement of the selected fissile fuel subassembly.
FIG. 1I is a block diagram showing details of a portion of the method of FIG. 1A.
1J is a view showing the rotation of the fission fuel sub-assembly.
Figure 1K is a block diagram showing details of a portion of the method of Figure IA.
FIG. 1L is a diagram showing an inverted sound of the fission fuel sub-assembly.
Figures 1M-1N are block diagrams detailing a portion of the method of Figure IA.
10 is a view showing a spiral movement of the sub-fission fuel assembly.
FIG. 1P is a block diagram showing details of a portion of the method of FIG. 1A.
FIG. 1Q is a diagram showing the axial movement of the fission fuel subassembly.
FIG. 1R is a view showing a substantially spherical shape of a fission propagating fire flame surface.
Fig. 1S is a diagram showing a continuous curved surface of a fission progressive wave flame surface.
Figure 1T shows a substantially rotationally symmetrical shape of the fission propagation flame surface.
Figs. 1U to 1V show a substantial n-fold rotational symmetry of the shape of the fission propagation flame surface.
FIG. 1W shows the asymmetric shape of the fission propagation wave flame surface.
Figures 1X-1F are block diagrams showing details of a portion of the method of Figure 1A.
Figure 2A is a block diagram of an exemplary method of controlling a fission progressive nuclear reactor.
Figures 2B-2M are block diagrams showing details of a portion of the method of Figure 2A.
Figure 3A is a block diagram of an exemplary system for determining movement of a fissile fuel subassembly.
Figures 3B-3C are block diagrams showing the details of the components of the system of Figure 3A.
4A is a block diagram of an exemplary system for moving a fission fuel subassembly.
Figures 4B-4C are block diagrams showing the details of the components of the system of Figure 4A.
5 is a block diagram partially illustrating a schematic form of an exemplary fission traveling wave reactor.
6A is a flow diagram of an exemplary method of operating a fission progressive wave reactor.
Figure 6B is a block diagram showing details of a portion of the method of Figure 6A.
Figure 7 is a flow chart of an exemplary method of operating a fission progressive wave reactor.
Figure 8 is a flow diagram of an exemplary method of operating a fission progressive wave reactor.
9 is a flow chart of an exemplary method of operating a fission traveling wave reactor.
10A is a flow diagram of an exemplary method of operating a fission reactor.
Figures 10B-10D are block diagrams showing details of a portion of the method of Figure 10A.

In the following detailed description, reference is made to the accompanying drawings, which form a part hereof. In the drawings, similar symbols typically represent similar elements unless the context clearly dictates otherwise. The illustrative embodiments set forth in the description, drawings, and claims are not intended to be limiting. Other embodiments may be used and other modifications may be made without departing from the spirit or scope of the subject matter presented herein.

Exemplary embodiments are directed to methods and systems for moving fuel assemblies in nuclear fission reactors, methods of operating nuclear fission traveling wave reactors, control methods of fission traveling wave reactors, control systems for fission traveling wave reactors, computer software program products for controlling fission traveling wave reactors, And a system for moving the fuel assembly.

An Overview of the Nuclear Fission Propagation Waves

Before describing the non-limiting embodiments presented here in detail, a brief overview of the fission propagation wave will be described. The fission progress wave is also known as the fission fission wave, but for the sake of clarity, it is referred to here as the fission propagation wave. Some of the following are discussed in the workshop of the Aspen District Change Research Institute held in July 2003, "Completely Automated Nuclear Power Reactors For Long-Run" by Edward Thurler, Muriel Ishikawa, Lowell Wood, A paper entitled "Term Operation: III. Enabling Technology for Large-Scale, Low-Risk, Affordable Nuclear Electricity" (UCRL-JRNL-122708 (2003) 30 June , Energy , The International Journal ), the contents of which are incorporated herein by reference.

In a "wave" that travels through the core of a fission-progressing nuclear reactor at a rate of about 1 cm per year, the fertile fission fuel material is propagated as a fissile fission fuel material, do.

Certain fissionable fuels designed for use in fission-progressing nuclear reactors are typically widely available, such as, but not limited to, uranium (natural, degraded or enriched), thorium, plutonium, or precombusted fission fuel assemblies. Other less widely used fission fuels may also be used, such as, but not limited to, other actinide elements or isotopes thereof. Some fission-progressing nuclear reactors expect long-term operation at full power for about 1/3 to 1/2 century or longer. Some fission-progressing nuclear reactors do not consider replacing nuclear fuels (instead they are believed to be buried at the end of their useful life), and some other fission-progressing nuclear reactors are expected to replace nuclear fuels, some of which occur during shutdown Some nuclear fuel replacements occur during operation at the plant. It is also expected that in some cases it would be possible to ban fission fuel reprocessing and reduce the likelihood of switching to military use and other problems.

Achieving 1/3 to 1/2 century (or longer) operation at maximum output without nuclear fuel replacement and simultaneously accepting the prohibition of reprocessing fission fuel can involve the use of fast neutron spectra. Moreover, the propagation of fission propagation waves enables a high average burn-up of unconcentrated actinide fuels, such as natural uranium or thorium, and allows the burning of fissile material from the fuel charge of the core Permits the use of relatively small " fission igniter " areas of suitable isotope enrichment.

Thus, the fission traveling wave reactor core may suitably include a fission firing igniter and a large fission burn-wave-propagating region. The fission-burning combustion wave propagation zone appropriately encompasses thorium or uranium fuel and functions according to the general principles of fast neutron spectral proliferation.

Fission propagation wave reactor core is a suitable breeder because of its efficient fission fuel utilization and minimization of isotope enrichment requirements. Also, because the high absorption cross-sectional area of the thermal neutron fission product does not eliminate the fission products and does not allow high fuel utilization of uranium isotope ²³⁸ U, typically thorium or more abundant in uranium-fueled embodiments, Fast neutron spectra are used appropriately.

Now, an exemplary fission traveling wave will be described. Propagation of a detonation burner through a fission fuel material can release power at a predictable level. Furthermore, if the material composition has sufficient time-invariant characteristics, such as the configuration found in typical commercial power generation nuclear reactors, continuous power production can be achieved at a stable level. Finally, if the traveling wave propagation speed can be adjusted externally in a practical manner, the energy release rate and hence the power production can be controlled as desired.

The nuclear engineering of the fission propagation wave is explained later. Inducing the fission of selected isotopes of actinide elements that are fissionable by neutron absorption of any energy can release nuclear energy at arbitrary material temperatures including arbitrarily low. The neutrons absorbed by the fissile actinide elements may be provided by a fission firing igniter.

One or more neutron emission per neutron absorbed on average by fission of virtually any actinide isotope can provide an opportunity for a divergent neutron-mediated nuclear fission chain reaction in such material. Typically, the number of neutrons emitted per absorption is expressed as η, where η = υσ _f / (σ _f + σ _c ), and υ is the number of neutrons emitted per fission. For each neutron that is absorbed (on average over a specific range of neutron energies), more than one neutron emission causes the atom of the non-fissile isotope to first be converted to a fissile atom by the initial neutron capture (neutron capture and subsequent beta decay ), And then further neutron fragmentation of the nucleus of the newly generated fissile isotope in the course of the second neutron scission uptake.

Most high Z (Z ≥ 90) nuclides, if on average, a single neutron from a given fission event is not fissile, but is radioactively captured in the nuclear fuel nucleus, and then the nucleus is converted into a fissile nucleus ) And can be used as a fission fuel material in a traveling wave reactor (or proliferation reactor) if a second neutron from the same fission event can be captured in a fissile atomic nucleus to induce a division. In particular, if any of these configurations is in a steady state, sufficient conditions for propagating the fission traveling wave in a given material can be satisfied.

Due to the beta decay of intermediate isotopes in the process of converting a nuclear fuel nucleus into a fissile nuclear nucleus, the fraction of the fissile material that can be used for fission is limited. Therefore, the characteristic speed of the wave progress is limited by a half-life of about several days or several months. For example, the characteristic velocity of the wave process is dependent on the distance the neutron travels from its fission-birth to the radioactive capture in the nuclear fuel nucleus (ie, the mean free path) versus the nuclear fissionable nucleus (The longest remaining nucleus in the chain reaction of beta-decay). The characteristic fission neutron-transport distance in a normal density actin group is approximately 10 cm and the half-life of beta decay is in most cases 10 ⁵ to 10 ⁶ seconds. Therefore, in some cases, the speed of the characteristic waves is 10 ^-4 to 10 ^-7 cm / sec. Such a relatively slow running speed indicates that this wave can be characterized as a traveling wave or a wavy wave rather than an anomaly wave.

If the traveling wave tries to accelerate, the concentration of the fissile nucleus is much lower before the center of the wave, so that the leading-edge of the traveling wave is a more pure nuclear fuel material (which is relatively lossy from a nuclear engineering point of view) . Thus, the leading edge of the wave (here referred to as the " burnfront ") loses or slows down. Conversely, if the wave is slow and the conversion rate is maintained at 1 or more (ie, the rate of proliferation is greater than the rate of fission), the local concentration of fissile nuclei arising from continuous beta decay is increased and fission and neutron generation The local rate rises and the leading edge of the wave, the flame side, is accelerated.

Finally, if the heat associated with fission is quickly removed from all parts of the constituent of the initial nuclear fuel material in which the waves are propagating, the propagation at any low material temperature, even if the temperature of both the neutron and fission nuclei is about 1 MeV Can happen.

Conditions for generation and propagation of such fission propagation waves can be realized by readily available materials. The fissile isotopes of actinide elements are absolutely and relatively rare on Earth, compared to the nuclear fuel isotopes of actinide elements, but fissile isotopes can be concentrated, concentrated and synthesized. In initiating the fission chain reaction, it is well known to use both naturally occurring and artificially fissile isotopes such as U ²³³ , ²³⁵ U, and ²³⁹ Pu, respectively.

A review of suitable neutron cross-sections suggests that fission propagation waves can burn large portions of naturally occurring actinide core, such as ²³² Th or ²³⁸ U, if the neutron spectra in the waves are 'stiff' or 'fast' . That is, if the energy of the neutrons that maintain the chain reaction in the wave is not very small compared to about 1 MeV, which is the energy that neutrons have when they come out of the initial fission piece, the local mass fraction of the fission product is local , It is possible to avoid a relatively large loss of local neutron economics over time and space (recall that one mole of fissile material is fission converted into two moles of fission generating nuclei). Even neutron losses for typical neutron reactor structural materials such as Ta with favorable high temperature properties can be drastically reduced at neutron energies below 0.1 MeV.

Other considerations include the (relatively small) deviation (ν) of the neutron multiplicity of the fission due to incident neutron energy and the contribution of all neutron absorption events (resulting in fission only, not gamma Ratio (?). For each fissile isotope of the reactor core, there is no neutron leakage from the core or parasitic absorption in the core body (e.g., in the fission product), the algebraic sign of the function? (? -2) Compared to the mass budget of the isotope, it constitutes a condition for the feasibility of fission propagation in nuclear fuel materials. The algebraic sign is usually a positive sign for all fissile isotopes of interest, ranging from about 1 MeV upward to below the resonant capture region.

The physical quantity α (ν-2) / ν sets the upper limit of the proportion of neutrons that can be lost due to leakage, parasitic absorption or geometric divergence during progressive wave propagation among all the neutrons generated by fission. Note that the above ratio for the major fissile isotopes ranges from 0.15 to 0.30 over the range of neutron energies (approximately 0.1 to 1.5 MeV) commonly found in the construction of all actinide isotopes. Unlike the situation where the parasitic losses due to fission products, which are commonly seen in neutrons with high (thermal) thermal energy, exceed 1 to 1.5 parasitic losses of transition from nuclear fuel to fissionable by 10 times, Over the MeV neutron energy range, the fissionable element generation by capture in the nuclear fuel isotope is favored by 0.7 to 1.5 times the capture of the fission product. The former suggests that the conversion of nuclear fuel materials to fissile materials is only possible from 1.5 to 5% at or near thermal neutron energy, while the latter is 50% when approaching the neutron spectrum of fission energy Suggesting that a higher conversion rate is expected.

Given the conditions for the propagation of fission propagation waves in some approaches, neutron leakage can be neglected in the case of very large "magnetically reflective" actinide constructions. When there are sufficiently large numbers of two relatively rich earth-active actinides, ²³² Th and ²³⁸ U, which are the unique and important (ie, the longest remaining) isotopes of naturally occurring thorium and uranium, respectively, It can be done.

Specifically, for these actinide isotopes the neutron transfer is carried out before the neutron energy is reduced to less than 0.1 MeV (and, as a result, the potential for capture at the fission product nucleus can not be ignored) ), Capture at the nuclear fuel atom isotope nucleus, or fission of the fissile isotope. The concentration of the fission product nucleus may approach or exceed the concentration of the nuclear fuel material and the fissile nucleus concentration may be present in a quantitatively and substantially reliable amount so that the concentration of the fission product or nuclear fuel You will find that it may be smaller in size than the lesser of the sex material. In consideration of the appropriate neutron diffusion cross-sectional area, the composition of the actinide element, which is sufficiently vast to be substantially infinitely thick, i.e. self-reflecting, in order to cause neutron disruption in the radial dimension, has a density-radius product of > 200 gm / cm ² , That is, the solid density ²³⁸ U- ²³² Th radius >> 10-20 cm.

The proliferation and combustion waves proliferate the new fissile material of the 1-2 average free pathway to yet unburned fuel and provide sufficient surplus neutrons to effectively replace the burned fission fuel in the wave. The 'ashes' following the peak of the combustion wave are substantially 'neutronically neutrally', since the neutron reactivity of the fission site is exactly balanced by the parasitic absorption of the structure and the inventory of the fission products in addition to the leakage amount. This wave is behaving very steadily if the amount of fissile atomic stock at the center and immediately before the wave does not change with time when the wave propagates and if the amount of fissile atomic stock is reduced, Disappearing ', whereas if the fissile atomic stock increases, the wave can be said to be' accelerating '.

Thus, the fission propagation wave can be propagated and maintained in a substantially steady-state condition over a long period of time, in the construction of naturally occurring actinide isotopes.

In the above description, as a non-limiting example, consider a cylinder of natural uranium or thorium metal having a diameter of less than about 1 meter, provided that if an effective neutron reflector is used, the cylinder may be substantially smaller in diameter, It is possible to stably propagate the traveling wave of the fission over the axial distance. However, propagation of fission propagation waves should not be construed as limited to cylindrical, symmetric geometry, or single connection geometry. In this regard, a further embodiment of an alternative geometry of a nuclear fission propagation reactor core is described in " AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION " Hyde, Muriel W. Ishikawa, Nathan Blood, Myhubold and Lowell El. U.S. Patent Application No. 11 / 605,943, filed November 28, 2006, the contents of which are incorporated herein by reference.

Propagation of the fission propagation wave has a close relationship with the embodiment of the fission propagation wave reactor. As a first example, local material temperature feedback can be imposed on the local nuclear reaction rate, at an acceptable cost in the neutron economics of traveling waves. This large negative temperature coefficient of neutron reactivity provides the ability to control the traveling speed of the traveling wave. If the thermal power drawn from the combustion fuel is very small, the temperature of the combustion fuel rises and the temperature-dependent reactivity decreases, correspondingly the fission rate at the center of the wave decreases and the time-dependent wave equation only reflects a very small axial velocity do. Likewise, if the thermal power removal rate is large, the material temperature decreases, and the neutron reactivity rises, the neutron economics inside the wave do not decline relatively, and the wave propagates relatively rapidly in the axial direction. Details regarding exemplary implementations of temperature feedback that may be incorporated into embodiments of reactor core assemblies are provided in " CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR " Hyde, Muriel W. Ishikawa, Nathan Blood, Myhubold and Lowell El. U.S. Patent Application No. 11 / 605,933, filed November 28, 2006, the contents of which are incorporated herein by reference.

As a second example, which is closely related to the propagation of fission propagation waves for an embodiment of a fission progressive nuclear reactor, some of the total fission neutron products in the fission propagation reactor can be used. For example, a reactive control system, such as, but not limited to, a neutron absorber in a control rod or a thermostat module at a local material temperature, can use about 5 to 10% of the total fission neutron product in a fission progressive reactor. Total Fission in a Fission Propagation Reactor Another 10% or less of the neutron product can be lost as it is parasitically absorbed into a high performance, high temperature structural material (eg, Ta, W, or Re) used in the structure of a fission traveling wave reactor . This loss occurs to achieve the desired thermodynamic efficiency in the conversion of the electric furnace and to obtain a high system safety performance index. Z of these structural members, such as Ta, W, and Re, is about 80% of the Z of the actinide element, and thus the radioactive capture cross-sectional area for these structural members for high energy neutrons is not much smaller than the radioactive capture cross-sectional area of the actinide element. Total Fission in a Fission Reactor Reactor The last 5-10% of the neutron product can be lost as it is parasitically absorbed into the fission product. However, it can be expected that the spectrum is similar to that of a sodium-cooled fast reactor in that the parasitic absorption only results in a loss of about 1-2%. As noted above, the fact that about 70% of the total fission neutron product is sufficient to maintain the propagation of traveling waves in the absence of leaks and sudden geometric exudation demonstrates that neutron economics are sufficiently abundant.

As a third example, which is closely related to the propagation of fission propagation waves to embodiments of fission-progressing nuclear reactors, it is possible to estimate the amount of initial actinide fuel stock (about 20% to about 30%, or in some cases 40% High to about 80%), the mined fuel can be used with high efficiency without requiring reprocessing.

It is noted that the neutron flux from the strongest combustion region behind the flame side plays a role in propagating the fission propagation wave by propagating the fissionable isotope enriched region at the leading edge of the flame side. After the flame side of the fission propagation wave sweeps a certain mass of fuel, the radioactive capture of the neutron is much more likely to occur at the available nuclear fuel nucleus than at the fission product nucleus, and the ongoing fission generates an increasingly larger mass of fission products As long as the fissionable atomic concentration continues to rise. At any given moment, the specific gravity of the nuclear power production is largest in this region of the fuel cell stack.

Much behind the progressive flame side of the progressive wave of fission propagation, the concentration ratio of the fission product nucleus to its fission product (whose mass, on average, is close to half of the fissionable nuclear mass) It goes up to the value that matches the rain. As a result, " local neutron reactivity " may approach a negative value, or may be negative in some embodiments. It is also expected that in some embodiments non-fissionable neutron absorbers such as boron carbide, hafnium or gadolinium are added to ensure that " local neutron reactivity " is negative.

In some embodiments of a fission traveling wave reactor, all fission fuels used all the time in the reactor are installed during the manufacture of the reactor core assemblies. Also, in some configurations, spent fuel is never removed from the reactor core assemblies. In one technique, such an embodiment may operate without allowing access to the reactor core after fission ignition and possibly after the end of propagation of the flame surface.

In some other embodiments of fission progressive nuclear reactors, all fission fuels that are used all the time in a reactor are installed during the manufacture of the reactor core assemblies, and in some configurations the spent fuel is never removed from the reactor core assemblies. However, as described below, at least a portion of the fission fuel may be moved or scrambled between respective positions within the reactor core. Movement or intermixing of at least a portion of this fissionable fuel may be performed to achieve the purpose described below.

However, in some other embodiments of a fission traveling wave reactor, additional fission fuels may be added to the reactor core assemblies after fission ignition. In some embodiments of the fission progressive nuclear reactor, spent fuel can be removed from the reactor core assembly (and in some embodiments, removing spent fuel from the reactor core assembly is accomplished while the nuclear fission propagation reactor is in operation at the plant can do). Such exemplary fuel replacement and fuel removal is described in " METHOD AND SYSTEM FOR PROVIDING FUEL IN A NUCLEAR REACTOR " Hyde, Muriel Wai. Ishikawa and Nathan P. Myhubold and Lowell El. U.S. Patent Application No. 11 / 605,848, filed November 28, 2006, the contents of which are incorporated herein by reference. Irrespective of whether or not the spent fuel is removed, preloading the loaded fuel causes the fission traveling waves to sweep any given axial element of the actinide 'fuel' and convert this element to a fission product 'ash' , High density actinide elements can be replaced with low density fission products without changing the overall volume in the fuel element.

In a general example, oscillations to the ²³² Th or ²³⁸ U fuel loading of a fission traveling wave can be initiated using a 'fission igniter module' such as (but not limited to) a fission fuel assembly with a fissile isotope enriched . An exemplary fission igniter module and method of oscillating a nuclear fission propagation wave is described in " NUCLEAR FISSION IGNITER " Alfred, John Rogers, and Ronald Reagan. Hyde, Muriel Wai. Ishikawa and David. McCalliz, Natan. Myhubold, Charles Whitmer and Lowell El. U.S. Patent Application No. 12 / 069,908, filed Feb. 12, 2008, the contents of which are incorporated herein by reference. The higher the degree of concentration, the more compact the module can be created, and the minimum mass module can use the moderator concentration gradient. In addition, the design of the fission igniter module may be determined in part by non-technical challenges, such as inhibiting the material from being useful for military use in various scenarios.

In another technique, an exemplary fission firing device may have other types of reaction sources. For example, other fission igniters may include "burning embers", such as fission fuels, in which fissile isotopes are enriched by exposure to neutrons within a fission propagation-type fission reactor. Such " burning depletion " can function as a fission firing igniter despite the presence of large amounts of fission product " ashes ". In another technique for oscillating the fission propagation wave, the fission igniter module, in which the fissile isotope is enriched, is a high energy ion (quantum, neutrons, alpha particles, etc.) or other neutrons using an electrical drive source of electrons It may also be used to supplement the source. In one exemplary technique, a particle accelerator, such as a linear accelerator, may be disposed to provide a high energy proton to the intermediate material that can subsequently provide the neutron (e.g., via fracture). In another exemplary technique, a particle accelerator, such as a linear accelerator, is placed (hereinafter referred to as a " particle accelerator ") to provide high energy electrons to an intermediate capable of providing the neutron (e.g., by electrical fission and / . Alternatively, other known neutron emission processes and structures, such as an electrically induced fusing technique, may provide neutrons (e.g., 14 MeV neutrons from DT fusion), whereby the neutrons are fissionable isotopes Can be used to initiate propagation of the fission wave in addition to the concentrated fission igniter module.

Since we have described the nuclear field of the fuel cell and the progressive wave of fission, we explain more about the "fission ignition" and maintenance of the fission propagation wave. ^An exemplary fissile igniter located at the center where the fissile material, such as ²³⁵ U or ²³⁹ Pu, is suitably enriched can be removed from the neutron absorber (e. G., By electrical heating commanded by the operator or by the recovery of one or more control rods) Borohydride, etc.) are removed, and the fission igniter becomes a neutronically critical state. The local fuel temperature rises to a predetermined temperature and is thereafter adjusted by a reactor cooling system and / or a reactive control system or a local temperature auto-regulating module, etc. This module is called " AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION " a. Hyde, Muriel Wai. Ishikawa and Nathan P. Myhubold and Lowell El. U.S. Patent Application No. 11 / 605,943, filed November 28, 2006, the contents of which are incorporated herein by reference. The neutrons from the high-velocity fission of ²³⁵ U or ²³⁹ Pu are mostly ²³⁸ U or ²³² Th Lt; / RTI >

By introducing a radial density gradient of refractory modifiers such as graphite into the fission igniter and the surrounding fuel region, the enrichment of uranium enrichment of the fission igniter is not much greater than the enrichment of uranium in light water reactor (LWR) fuel You will notice that you can reduce it. By increasing the density of the moderator, it is possible to burn the low-enriched fuel sufficiently, while lowering the moderator density enables the fission propagation to take place effectively. Thus, the optimal fission firing design is a trade-off between nuclear spreading stability and minimum delay time, from the initial criticality until the maximum standard output is available at the fully charged fuel stack of the core And the like. As the concentration of fission igniters decreases, more proliferative generations become, and the delay time increases accordingly.

In some embodiments, the maximum reactivity of the reactor core assemblage is slowly reduced in the first stage of the fission ignition process because the total inventory of the fissile isotope is increased, but the dispersion of the total inventory into the space is increasing. As a result of the selection of the initial fuel geometry, fuel concentration versus location, and fuel density, the maximum reactivity can be adjusted to be slightly positive even when the reactivity reaches a minimum value. As soon as the fissile isotope stock in the proliferation zone substantially exceeds the isotopic inventory remaining in the fission igniter, the maximum reactivity begins to increase rapidly toward its maximum immediately thereafter. In many cases, a quasi-spherical annular shell then provides the maximum output throughput. At this point, the fuel charge of the reactor core assembly can be said to have been "ignited".

We will now also discuss the propagation of fission propagation waves, also referred to herein as "fission combustion". In the configuration described above, the spherical diverging shell of maximum non-power output continues radially from the fission igniter toward the outer surface of the fuel filler section. When the spherical diverging shell reaches the outer surface of the fuel filler portion, the spherical diverging shell is naturally broken into two sphere-shaped surfaces, and these surfaces propagate in one of two opposite directions along the axis of the cylinder. At this point, the thermal power generation potential of the core can be maximized. This gap is characterized by an oscillation period of two fission propagation wave flame planes propagating in the axial direction. In some embodiments, the center of the fuel filler portion of the core is ignited, resulting in two waves propagating the opposite way. This configuration doubles the mass and volume of the core at which output production occurs at any given time, thereby doubling the maximum peak power generation of the core to quantitatively minimize heat transfer challenges. However, in other embodiments, the fuel charge portion of the core is ignited at or near one end as needed for a particular application. Such a technique may cause a single propagation wave in some configurations.

In another embodiment, the fuel charge portion of the core can be ignited at a plurality of locations. In yet another embodiment, the fuel charge portion of the core is ignited at any three-dimensional location in the core as needed for a particular application. In some embodiments, two propagating fission traveling waves will be generated and propagated away from the fission firing site, but depending on the geometry, the fission fuel composition, the behavior of the neutron deformation control structure, or other considerations, , 1, 3, or more) of fission traveling waves can be initiated and propagated. However, for purposes of understanding and brevity, we will now discuss (but not limited to) propagation of two fission progressive flame surfaces.

After two traveling waves have passed through two wave-like waves reaching or approaching both ends, the physical properties of the atomic power generation are typically time-invariant in a frame of any wave. The velocity at which the wave travels through the fuel is proportional to the local neutron flux, and furthermore it is linearly dependent on the thermal power required by the reactor core assembly due to the aggregation action of the neutron flux of the neutron control system's fission wave. In one technique, the neutron control system can be implemented using a thermostat module (not shown), which is referred to as " CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR " Hyde, Muriel Wai. Ishikawa and Nathan P. Myhubold and Lowell El. U.S. Patent Application No. 11 / 605,933, filed November 28, 2006, the contents of which are incorporated herein by reference. In another technique, the neutron control system can be implemented with one or more rods containing a neutron absorber and moving by one or more control rod drive mechanisms.

If more power is required from the reactor through the cryogenic coolant entering the core, the temperature at both ends of the core (in some embodiments, closest to the coolant inlet) in some embodiments is at the design setpoint of the thermostat module So that the neutron absorber is withdrawn from the corresponding subgroup of the thermostatic module of the core, thereby increasing the local thermal power output to a point where the local material temperature is raised to the set point of the local thermostatic module , The local neutron flux can be increased. In some other embodiments, temperature control can be performed by inserting the control rods as needed in response to changes in the monitored temperature.

However, in the embodiment having the two flame surfaces, this process is not very effective for heating the coolant until the two divided flows move toward the two nucleate flame surfaces. At this time, two parts of the core of the fuel core of the reactor core, that is, two parts that can produce significant levels of nuclear power if not suppressed by the neutron absorber of the thermostatic module, And serves to heat the coolant to a temperature specified by the design set point of the thermostat module, irrespective of the temperature of the reached coolant. Thereafter, the two coolant flows travel through the two sections of the already burned fuel toward the center of the two flame surfaces, thereby eliminating residual fission and residual heat release from the residual fission, It is going out from the center of all the chapters. This configuration primarily "trims" the excess neutrons from the back of each flame surface, thereby promoting the propagation of the two flame surfaces toward both ends of the fuel cell.

Therefore, the neutron engineering of the core of this configuration can be considered to be substantially self-regulating. For example, in the case of a cylindrical core embodiment, the nuclear engineering technique of the core is that when the product of the fuel density-radius of the cylindrical core is greater than 200 gm / cm 2 (i.e., in the case of a fairly fast neutron spectrum, When the mean free path of neutron-induced nuclear fission in the core is 1 to 2), it can be considered to be substantially self-regulating. One function of the neutron reflector in such a core design is to provide the outer portion of the reactor, such as the radiation shielding of the reactor, the structural support, the outermost shell, and the control rod (if provided) and the thermostat module (if provided) Such as (but not limited to) a reactive control system. The neutron reflector can also affect the performance of the core by increasing the propagation efficiency and the power output of the outermost portion of the fuel. Such an effect can improve the economic efficiency of the reactor. The outermost portion of the fuel pack is not used because of its low overall energy efficiency, but the isotopic burning level is comparable to the burning level at the center of the fuel pack.

Although the neutron engineering of the core in the above-described configuration may be considered substantially self-regulating, other configurations may include, for example, one or more control rods, such as one or more control rods that contain a neutron absorber, Can be operated under the control of a reactor control system having a suitable electronic controller with a circuit and a suitable electro-mechanical system.

Finally, the irreversible negativity of the neutron reactivity of the core can be performed at any time by injecting a neutron poison into the coolant stream as needed. For example, when a small amount of a material such as BF _{3 is added} to the coolant stream together with a volatile reducing agent such as H ₂ in some cases, 2BF ₃ + 3H ₂ -> 2B + 6HF, which is a slow chemical reaction in other cases, , The metal boron can be deposited substantially uniformly on the inner wall of the coolant pipe which exits the core of the reactor. Subsequently, boron is a highly refractory base metal and will typically not migrate from the deposition site. If boron is present in the core substantially uniformly in an amount of less than 100 kg, the neutron reactivity of the core can be negated for a very long period of time without using a power mechanism near the reactor.

In general, those skilled in the relevant art will appreciate that the various aspects described herein may be implemented individually and / or collectively by a wide variety of hardware, software, firmware, and / or any combination thereof, &Quot; and " Thus, " electrical circuit " as used herein includes, but is not limited to, an electrical circuit having at least one discrete electrical circuit, an electrical circuit having at least one integrated circuit, an electrical circuit having at least one special purpose integrated circuit Circuitry, a general purpose computer configured by a computer program that at least partially accomplishes the processes and / or devices described herein, or a process and / or device described herein, An electrical circuit forming a memory device (e.g., memory (e.g., RAM, flash memory, ROM, etc.)), and / And an electrical circuit forming a device (e.g., modem, communication switch, photoelectric device, etc.). Those of skill in the relevant art will recognize that the subject matter described herein may be implemented in analog or digital fashion, or some combination thereof.

In general, those skilled in the relevant art will recognize that the various embodiments described herein may be practiced with a wide variety of electrical components, such as hardware, software, firmware, and / or a combination thereof; And various types of electromechanical systems having a wide variety of components that can affect mechanical forces or motions, such as a rigid body, a spring or torsion body, a hydraulic device, an electromagnetic drive, and / or a combination thereof. / RTI > and / or < / RTI > Thus, " electromechanical system " as used herein includes, but is not limited to, an electrical circuit operatively coupled to a transducer (e.g., an actuator, a motor, a piezoelectric crystal, a microelectromechanical system An electrical circuit having at least one integrated circuit, an electrical circuit having at least one special purpose integrated circuit, a general purpose computing device configured by a computer program (e.g., A microprocessor configured by a general purpose computer configured by a computer program that at least partially accomplishes the device, and / or a computer program that at least partially accomplishes the process and / or apparatus described herein), a memory (E. G., Memory (e. G., RAM, flash memory, ROM, etc.) As, a communication device, an electronic circuit which forms the (e. G., A modem, communications switch, optical devices, etc.), and / or non-electrical (非 電氣) analogues, such as optical or other analogs. Those skilled in the relevant art will appreciate that examples of electromechanical systems include, but are not limited to, various consumer electronics systems, medical equipment, as well as a motorized transportation system, a factory automation system, a security system, and / ≪ / RTI > Those of skill in the relevant art will recognize that the electromechanical machines employed herein are not necessarily limited to systems having both electrical and mechanical actions unless otherwise indicated in the context.

Exemplary embodiments

Having thus far described a brief overview of the initiation and propagation of fission propagation waves, the exemplary embodiments will now be described as non-limiting examples.

The following is a series of flowcharts depicting an implementation. For ease of understanding, a flow diagram illustrates a flow diagram in which an initial flow diagram provides an implementation through an exemplary implementation, and a subsequent flow diagram depicts an alternative flow diagram as an alternative configuration operation or an alternative configuration operation in which one or more previously provided flow diagrams are constructed. And / or an extended implementation. Those skilled in the relevant art will appreciate that the description methods employed herein (e.g., beginning with the description of the flowcharts providing exemplary implementations, and then providing additional and / Method) will generally allow a quick and easy understanding of various process implementations. It will also be appreciated by those skilled in the relevant art that the description used herein is also well adapted to a modular and / or object oriented programming design paradigm.

Referring now to FIG. 1A, an exemplary method 10 for operating a fission traveling wave reactor is provided, in accordance with an overview. Referring further to FIG. 1B, an exemplary fission traveling wave reactor core 12 of a fission traveling wave reactor is shown by way of example only, without limitation. The fission fuel sub-assembly (14) is contained in the reactor core assembly (16). For clarity, FIG. 1B shows a portion of the fission fuel sub-assembly 14 that may be contained in the reactor core assembly 16.

The reference skeleton is defined within the reactor core assembly 16. In some embodiments, the reference skeleton can be defined as an x-dimension, a y-dimension, and a z-dimension. In some other embodiments, the reference skeleton may be defined as a radial dimension and an axial dimension. In some other embodiments, the reference skeleton may include an axial dimension and a lateral dimension.

In some embodiments, the fission fuel sub-assembly 14 may be an individual fission fuel element, such as a fission fuel rod, plate, sphere, or the like. In some alternative embodiments, the fission fuel sub-assembly 14 may be a fissile fuel assembly, i.e., two or more individual fissile fuel elements grouped into an aggregate. Regardless of the embodiment of the fission fuel subcollector 14, the fission fuel material contained in the fission fuel subcollector 14 may be any suitable type of fission fuel material as described above.

Still as an overview, the method 10 begins at block 18. At block 20, the fission progressive wave flame surface 22 is propagated along the first and second dimensions in the fission fuel sub-assembly 14 within the reactor core assembly 16 of the fission progress wave reactor core 12 24). At block 26, a selected fissile fuel sub-assembly among the fissile fuel sub-assemblies 14 is disposed at each first location (e.g., at a first location) in a manner that defines the shape of the fission progressive flame surface 22 along the second dimension Lt; RTI ID = 0.0 > a < / RTI > first dimension toward each second position. The method 10 ends at block 28.

Exemplary details are now described as non-limiting examples.

The fission fuel sub-assembly (14) has a spatial relationship to the dimensions designated as the first and second dimensions. For example, in some embodiments, the fission fuel sub-assembly 14 may extend along a second dimension. In some embodiments, the second dimension is a y-dimension, i.e., an axial dimension. In some other embodiments, the second dimension may be an x-dimension, z-dimension, i.e., a lateral dimension.

Moreover, in some embodiments, the first dimension is substantially orthogonal to the long axis of the fission fuel sub-assembly 14. In some embodiments, the first dimension and the second dimension are substantially orthogonal to each other.

Various dimensions may be designated as the first dimension and the second dimension. For example, in some embodiments, the first dimension comprises a radial dimension and the second dimension may comprise an axial dimension. In some other embodiments, the first dimension comprises an axial dimension and the second dimension may comprise a radial dimension. In some embodiments, the first dimension comprises an axial dimension and the second dimension may comprise a lateral dimension. In some other embodiments, the first dimension comprises a lateral dimension and the second dimension may comprise an axial dimension. For a cylindrical core in which the assembly extends axially, such as in a typical commercial water reactor configuration, the first dimension may be a radial dimension and the second dimension may be an axial dimension. In other reactor configurations, such as the cannula type (CANDU) heavy water reactor, the fuel assembly can extend along the first dimension and move along the second dimension in the lateral or radial direction.

As shown in FIG. 1B, each position in the reactor core 12 can be characterized as a first position and a second position, depending on various attributes. In general, the location can be considered as a space near the region of the reactor core 12 around the fission fuel sub-assembly 14. The location may also be thought of as a space that generally encloses any given area of the reactor core 12, or may be thought of as the majority of the reactor core 12. For example, referring additionally to FIG. 1C, in some embodiments, the first position may include an outer position 30 and the second position may comprise an inner position 32. In some embodiments, As shown in FIG. 1C, in some embodiments, the inner and outer locations 32 and 30 may be defined by the geometric proximity of the reactor core 12 to the center. In some other embodiments, the inner and outer positions may be determined according to the neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position. In some other embodiments, the inner position and an outer position may be determined according to the reactivity of the _effective k from the inner position to be greater than the _effective k at the outer position. A typical embodiment of a traveling wave reactor may have an outward position including positions on the outside of the wave in the direction of propagating waves, while an inward position may include positions on which the fission traveling wave is propagating or already propagated.

Referring to FIG. 1D as another example, in some embodiments, the first position may include an inner position 32 and the second position may comprise an outer position 30. [ 1D, in some embodiments, the inner position 32 and the outer position 30 may be defined by the geometric proximity of the reactor core 12 to the center thereof. In some other embodiments, the inner and outer positions may be determined according to the neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position. In some other embodiments, the inner position and an outer position may be determined according to the reactivity of the _effective k from the inner position to be greater than the _effective k at the outer position. In another embodiment, the inner and outer positions can be described in terms of the dominant nuclear reactions occurring in that region. As a non-limiting example, the medial position may be characterized by predominantly fission reactions in the nuclear fuel material, and the medial position may be characterized by the predominance of the nuclear absorption response.

Regardless of characterizing the first position and the second position as an inner position or an outer position, the first position and the second position may be characterized according to other attributes. For example, in some embodiments, the first position and the second position may be located on both sides of a reference value along the first dimension. In some other embodiments, the first location and the second location may include at least one attribute that is substantially equivalent. For example, at least one property that is substantially equivalent may include geometric proximity to the center of the reactor core, neutron flux, reactivity, and the like.

Referring to FIG. 1E as a non-limiting example, the sub-assemblies selected from the fissile fuel subassemblies (not shown for clarity) define the shape of the fission progressive flame side 22 axially in accordance with the selected set of dimension constraints Can be controllably moved radially outward from each inboard position 32 toward each outboard position 30. In this way, There is shown an axial change in the shape of the fission propagating flame front 22 as a result of radial movement of a subset of fission fuels (not shown), by way of example only. The left figure shows the initial shape of the fission propagating fire flame surface 22. It will be appreciated that for clarity purposes, only a quarter of the perimeter of the fission progressive flame front 22 is shown.

In the middle drawing, the selected fissile fuel subassemblies (not shown) are arranged in such a way that the selected fissile fuel subassemblies (not shown) are operated for a predetermined time or according to a desired reactive parameter (e.g., After burning, it was moved radially from the inner position 32 to the outer position 30. The reactivity was shifted radially outward from the peak (shown in the left drawing) positioned radially at the inner position 32 to the outer position 30 (shown in the middle view).

When the fission traveling wave reactor core 12 is at the end of its lifetime, an additional fission fuel subassembly (not shown) may be moved radially outward from the inner position 32 to the outer position 30. As a result of this additional outward movement, the fissile fuel subassembly (not shown), located radially inward of the fission traveling wave reactor core 12, is located at a radially outward position of the fission traveling wave reactor core 12, Can be prevented from being burned more than the sub-assembly (not shown). As shown in the right figure, if a sufficient number of fission fuel sub-assemblies are moved radially outward as described above, the shape of the fission progressive flame surface 22 may be approximately a Bessel function. In addition, if a sufficient number of fission fuel subassemblies are moved radially outward as described above, all or substantially all of the fission fuel subassemblies in the fission traveling wave reactor core 12 will reach their respective combustion limits almost simultaneously Or access. In that case, the use of the fission fuel sub-assembly in the fission traveling wave reactor core 12 is maximized.

1F, the fission fuel sub-assemblies 14 selected from the fissile fuel sub-assemblies are arranged in a manner that axially defines the shape of the fission progressive flame surface 22 according to the selected set of dimensional constraints The fission fuel sub-assemblies 14 'selected from the fissile fuel subassemblies can be controllably moved radially outward from each inner position 32 toward each of the outer positions 30, To the respective inward position 32 toward the radially inner side. That is, the selected fissionable fuel sub-assemblies 14, 14 'are interchanged between the inner position 32 and the outer position 30.

There is shown an axial change in the shape of the fission progressive flame front 22 due to this interchangeable radial movement of the fissile fuel sub-assemblies 14, 14 ', as an example only, without intending to be limiting. The left figure shows the initial shape of the fission propagating fire flame surface 22. In the left figure, the fission fuel sub-assembly 14 has more fissile components than the fission fuel sub-assembly 14 '. For example, the fission fuel sub-assembly 14 may be part of an igniter assembly for a nuclear fission traveling wave reactor core 12. As another example, the fission fuel sub-assembly 14 may include a fissionable material fused from the nuclear fuel isotope material as a result of absorbing the high-speed spectral neutrons in the nuclear fission reactor core 12 and then converting it into a fission isotope . In contrast, the fission fuel sub-assembly 14 'has less fission components than the fission fuel sub-assembly 14. In some cases, the fission fuel sub-assembly 14 'may contain more nuclear fuel isotope components than the fission fuel sub-assembly 14. In that case, the fission fuel sub-assembly 14 'is more absorptive to fast spectral neutrons than the fission fuel sub-assembly 14.

In the right figure, the selected fission fuel sub-assembly 14 has moved radially outward from the inner position 32 to the outer position 30 and the selected fission fuel sub-assembly 14 ' And moved radially inward to position 32. After the fissile fuel sub-assemblies 14, 14 'are interchanged, the axial appearance of the fission progressive flame front 22 is aligned with the axis of the fission progressive flame front 22 before this interchange Directional appearance and became more uniform. As a result, in some embodiments, a substantially uniform appearance or uniform appearance can be achieved with respect to the fission progressive wave flame surface 22. In some other embodiments it may not be desirable to achieve a substantially uniform appearance or uniform appearance with respect to the fission progressive flame front 22. In that case, it may be desirable to relocate the fissile material or relocate the nuclear fuel isotope material. In some other embodiments, it may be desirable to extend the fission progressive flame front 22 along the radial dimension.

Referring to FIG. 1G, the shape of the fission progressive wave flame surface 22 can also be adjusted in radial dimension by moving the fission fuel subassembly 14, 14 'along the radial dimension, as described above with reference to FIG. IF Can be limited. The radial appearance of the fission propagation wave flame surface 22 can be considered to represent the neutron leakage current. The left and right views of FIG. 1G show respective views along axial dimensions corresponding to the left and right views of FIG. 1F, respectively.

Referring now to FIG. 1H, the fission fuel sub-assemblies 14 selected from the fissile fuel sub-assemblies are arranged in a manner that radially defines the shape of the fission progressive flame surface 22 according to the selected set of dimensional constraints. Position to the respective second position. ≪ RTI ID = 0.0 >

The left drawing shows the initial shape of the fission propagation wave flame surface 22 when viewed along the axial dimension. The selected fission fuel sub-assembly 14 is located at a first position (z, r, phi ₁ ). In the example shown for illustrative purposes, nuclear fission fuel consumption aggregate 14 has a first position for any reason, the first position may be determined so as to exceed the amount of the reactive required (z, r, φ _1), (z, r, φ ₁ ). ≪ / RTI > For example, the fission fuel sub-assembly 14 may be part of an igniter assembly for a nuclear fission traveling wave reactor core 12. As another example, the fission fuel sub-assembly 14 includes a fission material that is propagated from the nuclear fuel isotope material as a result of the high-speed spectral neutrons being absorbed in the nuclear fission reactor core 12 and then converted to fission isotopes can do. As a result, the fission progressive wave flame surface 22 can propagate too much in the radial direction at the first position (z, r, phi ₁ ).

As shown in the right figure, the selected nuclear fission fuel consumption aggregate 14 has a first position (z, r, φ _1), second position (z, r, φ ₂₎ to the side along the lateral dimensions (φ) direction from . The shape of the nuclear fission traveling wave flame front 22 is selected fission fuel consumption aggregate 14 has a first position (z, r, φ ₁₎ as a result of movement in the lateral direction to a second position (z, r, φ ₂₎ from Lt; RTI ID = 0.0 > radial < / RTI > The fissile element at the first position (z, r, φ ₁₎ a second position (z, r, φ ₂₎ a first position (z, r, φ ₁₎ due to the lateral movement of the selected fissionable fuel consumption aggregate as from And the fission component is added to the second position (z, r, phi ₂ ). As shown in the right figure, the shape of the nuclear fission traveling wave flame front 22 has a first position (z, r, φ ₁₎ were shorter along the radial dimension (r) in the vicinity of the second position (z, r, φ ₂ ) in the radial direction (r).

Controllably moving the selected fission fuel sub-body 14 from block first 26 toward each second position from each first position may involve one or more processes. For example, with reference to FIGS. 1I and 1J, in some embodiments, the fission fuel sub-assembly 14 selected at block 26 can be controlled from a first position to a second position along a first dimension May include rotating at least one selected fission fuel sub-assembly 14 in block 34, as indicated by arrow 36 (Figure IJ). It will be appreciated that rotating at least one selected fission fuel sub-assembly 14 at block 34 may be performed by any suitable in-core fuel handling system as needed. It may also be desirable to rotate the selected fission fuel subcollector 14 to minimize or prevent deformation of the reactor structural material, such as bending of the fission fuel subassembly.

As another example, referring further to Figures 1K and 1L, in some alternative embodiments, the fission fuel sub-assembly 14 selected at block 26 may be moved from a respective first position to a respective second position along a first dimension Controllably moving may include inverting at least one selected fission fuel sub-assembly 14 at block 38, as indicated by arrow 40 (FIG. 1L). It will be appreciated that reversing at least one selected fission sub-fuel assembly 14 at block 38 may be performed by any suitable in-core fuel handling system as needed. By inverting the fission fuel sub-assembly 14, the inlet of the fission fuel sub-assembly 14 (before flipping) can be at the outlet of the fission fuel sub-assembly 14 (after inverting), or vice versa. This flipping can result in axial axial equalization of the thermal stress and / or radiation effects on the fission fuel sub-assembly 14 at the end of the fission fuel sub-assembly 14. This optional radiation effect may be associated temperature and / or may be related to variations in the neutron flux at the axial end of the fission traveling wave reactor core 12. It will be appreciated that the flip of the fission fuel subassembly 14 results in both ends of the inverted fission fuel subassembly 14 moving from the first position to the second position with respect to the flip center point. However, in some cases it may be desirable to also change the position of the fuel assembly in the lateral direction as well.

It will also be appreciated that for any particular application, any one or more dimensional constraints may be selected as desired. For example, in some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along a second dimension.

In some other embodiments, the selected set of dimensional constraints may be a function of at least one flame surface reference. For example, the flame surface standard may include a neutron flux. In some configurations, the neutron flux may be associated with at least one selected fission fuel sub-assembly. In some other embodiments, the flame surface criterion may include poetic atom neutron fluence. In some configurations, the poetic atomic neutron flux may be associated with at least one selected fission fuel sub-assembly 14.

In some other embodiments, the flame front reference may include a degree of combustion. In some configurations, the degree of combustion may be associated with at least one selected fission fuel sub-assembly 14. [ In such an arrangement, it may be desirable to move the selected fission fuel sub-assembly 14 from a first position having a first burn rate to a second position having a second burn rate. If the selected fission fuel sub-assembly 14 is near the end of its useful life time, the first position is a position characterized by a high burnup rate and the second position is reduced (relative to the high burnup rate at the first position) Or a position having a burning rate of substantially zero value. In an embodiment where the fission fuel sub-assembly 14 is grown, the fission fuel sub-assembly 14 is moved from a first position having a low burnup rate (relative to the burnup rate at the first location) to a second location having a high burnup rate It may be desirable to move it.

In some other embodiments, the flame front reference may include a flame front position within the at least one selected fission fuel sub-assembly. The flame surface position can be characterized by the features of the fission traveling wave reactor core 12 or the fission fuel sub-assembly 14 therein. Such characteristics include, by way of non-limiting example, fission rate, proliferation rate, power output, temperature, reactivity, and the like.

It will be appreciated that the controllable movement of the selected fissile fuel sub-body at each of the first to the second positions toward the respective second position at block 26 may be performed in any desired manner for special applications. For example, referring further to FIG. 1M (and as shown in FIGS. 1C and 1D), in some embodiments, the selected fission fuel sub-assembly 14 at block 26 is moved from its respective first position Controllably moves the selected fission fuel sub-assembly 14 at block 42 in a radial direction along a first dimension from each first position to a respective second position . Radial movement at block 42 may be performed by any suitable in-core fuel handling system as desired.

1N and FIG. 10, at block 26, the selected fission fuel sub-assembly 14 is controllably moved from its respective first position toward its respective second position along a first dimension May comprise controllably moving the selected fission fuel sub-body at block 44 in a spiral manner along a first dimension from each first position to a respective second position, as indicated by arrow 46. Spiral movement at block 44 may be performed by any suitable in-core fuel handling system as desired.

1P and 1Q, the selected fission fuel sub-assembly 14 at block 26 is controllably moved from its respective first position toward its respective second position along a first dimension To controllably move the fission fuel sub-assembly 14 selected in block 48 axially along the first dimension from each first position toward each second position, as indicated by arrow 50 . Axial movement at block 48 may be performed by any suitable in-core fuel handling system as desired.

The shape of the fission progressive wave flame surface 22 may include any parameters related to the fission progressive flame surface 22, such as, but not limited to, neutron flux, momentary flux neutrons, flammability, and / or reactivity ≪ / RTI > any of which may be present). It will also be appreciated that the fission propagation flame surface 22 may have any shape desired for special applications. With further reference to FIG. 1R as an example, in some embodiments, the shape of the fission progressive wave flame surface 22 may be substantially spherical. In some other embodiments, with further reference to FIG. 1S, the shape of the fission progressive wave flame surface 22 may be substantially coincident with the selected continuously curved surface (continuous curved surface). In some embodiments, with further reference to FIG. 1T, the shape of the fission progressive flame front 22 may be substantially rotationally symmetric about the second dimension. In some other embodiments, with further reference to Figures 1U and 1V, the shape of the fission progressive flame front 22 may have a substantial n fold rotational symmetry around the second dimension.

It is known in the art that maintaining a substantially constant " flat " combustion profile (e.g., a Bessel function) across the reactor core minimizes power peaking between the fission fuel subassemblies within the core and improves fuel utilization have. As described above, in a traveling wave fission nuclear reactor, the combustion region of a reactor tends to expand in size due to a high conversion rate. The combustion zone is maintained as a sufficient feed-nuclear material, such as a nuclear fuel isotope material or a fissile material, to maintain a high conversion rate.

It will be appreciated that in some reactor configurations it may be advantageous to move the fission fuel sub-assemblies as described above, in order to maintain the desired reactor flame surface characteristics. For example, moving the fissile fuel subassembly radially to the combustion region may act to supply a nuclear fuel isostatic material or fissile material to the reaction zone. Moving the fissile fuel subassemblies radially outward can be used to move the fissile fuel subassemblies that reach their combustion limits outside the high neutron activity area. Radial outward movement can also be used to lower the power density of the combustion region by diffusing fissionable and combustible fissionable fuel materials into the prior non-combustion region. It will be appreciated that radial movement combined with helical movement enables a finer spatial increase of radial movement coupled with azimuthal movement for different flame surface configurations. It will also be appreciated that in some cases the fission fuel subassembly may be exchanged (or interchanged) with the fission fuel subassembly at another location. In such a case, the nuclear fuel isotope material from the nuclear fuel blanket region can be replaced with a well combusted material from the reactor combustion region. In other cases, the fission fuel material may be exchanged from an adjacent reactor core location so that two or more fissionable fuel subassemblies exchange positions.

In some embodiments, with further reference to FIG. 1W, the shape of the fission progressive wave flame surface 22 along the second dimension may be asymmetric. In some configurations, the shape of the fission progressive flame front 22 may be rotationally asymmetric around the second dimension.

1X, the method 20 may also include initiating the fission progressive wave flame surface 22 with a fission progressive wave lighter assembly (not shown) at block 52. In some embodiments, An exemplary example of initiating a fission propagation wave with a fission progressive wave lighter assembly has been described above and will not be repeated here. 1 Y, at block 54, prior to controllably moving the selected fission fuel sub-assembly from its respective first position toward each second position along a first dimension, at least one fission progressive wave igniter assembly is removed . 1Z, in some embodiments, before controllably moving the selected fission fuel sub-assembly from its respective first position toward its respective second position along a first dimension, at least one fissure Removing the traveling wave lighter assembly removes at least one fission progressive wave lighter assembly before controllably moving the selected fission fuel subassembly from its respective first position toward each second position, 2 < / RTI > position.

1AA, at block 58, a fission progressive wave reactor is configured to move the selected fission fuel subassembly from the first position to each second position, prior to controllably moving the selected fission subassembly along the first dimension. To be in a critical state. For example, with further reference to FIG. 1 AB, in some embodiments, bringing the fission progressive wave reactor into a critical state at block 58 may include inserting the neutron absorber into the reactor core at block 60.

Referring further to Figure 1AC, in some embodiments, at block 62, the selected fissionable fuel subassembly is moved to a criticality after controllably moving along a first dimension from a respective first position to a respective second position, Can be re-established. With further reference to FIG. 1 AD, in some embodiments, re-establishing the threshold at block 62 may include removing at least a portion of the neutron absorber material from the reactor core at block 64.

1AEE, at block 66, the fission progressive wave reactor is configured to move the selected fission fuel subcollector from its respective first position to each second position, prior to controllably moving the selected fission fuel subassembly along the first dimension It may be suspended temporarily. With further reference to FIG. 1AF, at block 68, the fission progressive wave reactor can be reactivated after controllably moving the selected fission fuel subassembly from its respective first position toward its respective second position, along a first dimension.

Referring now to FIGS. 2A and 1B, an exemplary method 200 for controlling a fission progressive wave reactor propagating along a first and second dimension of a fission progressive wave flame surface 22 is provided. The method 200 begins at block 202. At block 204, the preferred shape of the fission progressive flame front 22 is determined along the second dimension within the fission fuel subset 14 according to the selected set of dimensional constraints. At block 206, the movement of the selected fission fuel sub-assembly 14 is determined along the first dimension from each first position toward each second position in a manner that responds to the desired shape.

With further reference to FIG. 2B, in some embodiments, at block 210, the existing shape of the fission progressive flame front 22 is determined. It will be appreciated that the determination of the existing shape of the fission progressive flame side 22 at block 210 may be performed as needed in connection with the determination of the desired shape of the fission progressive flame side 22 at block 204. In some embodiments, the determination of the existing shape of the fission progressive flame front 22 at block 210 may be performed prior to the determination of the desired shape of the fission progressive flame front 22 at block 204. In some other embodiments, determination of the existing shape of the fission progressive flame front 22 in block 210 may be performed substantially simultaneously with determination of the desired shape of the fission progressive flame front 22 in block 204. In some other embodiments, the determination of the existing shape of the fission progressive flame front 22 at block 210 may be performed after determining the desired shape of the fission progressive flame front 22 at block 204. The preferred shape can be determined as needed, including determination of the fission rate, estimated burn rate, proliferation rate, temperature distribution, power distribution, library operation history, and reactive value of the fission fuel material transferred at each location.

The selected fission fuel sub-assembly 14 may be moved to any desired destination for special applications such as, for example, establishing the desired shape of the fission progressive flame side 22 and / or maintaining the desired shape of the fission progressive flame side 22 . For example, in some embodiments, and with further reference to FIG. 2C, at block 206, the selected fission fuel sub-assembly 14 is moved from its respective first position toward each second position in a manner responsive to a desired shape, The crystals that move along the dimension include crystals that move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that establishes the desired shape can do. 2D, a crystal that moves a selected fission fuel sub-assembly 14 along a first dimension from a respective first position toward a respective second position in a manner responsive to a desired shape , And at block 214, move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that maintains the desired shape.

Among other things, it will be appreciated that it may be desirable to determine when to perform the desired movement. 2E, in some embodiments, at block 216, a selected dimension of the selected fission fuel sub-assembly 14 from each first location toward each second location in a manner responsive to a desired shape A decision is made as to when to move along.

In some embodiments, the selected fission fuel sub-assembly 14 may be moved. 2F, at block 218, the selected fission fuel sub-assembly 14 may be moved along the first dimension from each first position toward each second position in response to a desired shape.

It will be appreciated that some aspects of the method 200 are similar to some aspects of the method 10 described above. These similar aspects will be mentioned, but a detailed description thereof will be omitted for the sake of brevity.

1B, in some embodiments, the fission fuel sub-assembly 14 may extend along a second dimension. The first dimension may be substantially orthogonal to the long axis of the fission fuel sub-assembly 14. The first dimension and the second dimension may be substantially orthogonal to each other.

Referring again to Figure IB as another example, the first dimension may comprise a radial dimension and the second dimension may comprise an axial dimension. In some other examples, the first dimension may comprise an axial dimension and the second dimension may comprise a radial dimension. Any type of fission reactor may include a fissile fuel subassembly extending across the entire axial dimension, wherein the plurality of fissile fuel subassemblies extends across the radial dimension. The fission propagation wave can propagate along the axial dimension at a different rate than in the radial dimension, in particular in a cylindrical reactor core configuration, depending on the divergence and power distribution of the fission traveling wave from the inner region to the outer region in this case. In this case, it is desirable to carry out the radial movement of the fissile fuel sub-assembly to preserve the wave shape and characteristics in the axial dimension. For example, propagation of fission propagation waves to the axial extent of the reactor zone will promote neutron leakage from the reactor core at the axial end of the reactor core. This leakage, as described above, reduces the nuclear fuel-fissile transition within the fission reactor. A fissile fuel subassembly having a flame side that expands to an undesirable axial location is moved radially so that the fissile fuel subassembly is located within the fissile fuel subassembly that reduces or limits additional flame side propagation to an undesirable location It is governed by neutron behavior at the site. In other cases, the fission fuel subassembly is moved radially based on the fission propagation of the axial dimension, so that the fissile material propagated into the axial region of the fission fuel subassembly can be used in other parts of the fission reactor core May be preferred. At certain axial locations, the flame surface may become non-uniform along the radial dimension through controlled movement of the fission fuel subassembly to create different concentrating zones, if desired. By placing a high concentration zone followed by a depleted or low concentration zone, neutron leakage can be increased from a high concentration zone to a low concentration zone, thereby facilitating conversion of the nuclear fuel isotope material to a fissile material. It will be appreciated that the movement may be performed to promote propagation in the first dimension while limiting propagation in the second dimension.

Referring back to Figure IB as some other example, the first dimension may comprise an axial dimension and the second dimension may comprise a lateral dimension. As another example, the first dimension may include a lateral dimension and the second dimension may comprise an axial dimension.

1C, the first position may include an outer position 30, and the second position may include an inner position 32. As shown in FIG. Further, as described above, the inner position 32 and the outer position 30 can be determined in accordance with the geometric proximity to the center of the reactor core 12. The inner position 32 and the outer position 30 can be determined according to the neutron flux such that the neutron flux at the inner position 32 is larger than the neutron flux at the outer position 30. [ As described above, the inner position 32 and the outer position 30 can be determined according to the reactivity of the _effective k from the inner position 32, so that a larger than the _effective k from the outer position (30).

1D, the first position may include an inner position 32 and the second position may comprise an outer position 30. In some embodiments, The inner and outer locations are chosen such that the geometric proximity to the center of the reactor core 12 and / or the k _effective at the neutron flux and / or medial position is such that the neutron flux at the medial position is greater than the neutron flux at the medial position Can be determined depending on the reactivity so that it is larger than k _effective at the outer position.

In some embodiments, as shown in Figure IB, the first position and the second position may be located on both sides of a reference value along the first dimension.

As also shown in FIG. 1B, in some embodiments, the first location and the second location may include at least one attribute that is substantially equivalent. For example, at least one attribute may include geometric proximity to the central region of the reactor core 12, neutron flux, and / or reactivity.

2G, at decision block 206, a decision is made to move the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position along a first dimension, at block 220 And may include crystals that rotate at least one selected fission fuel sub-assembly (14). 2H, at decision block 206, a determination is made to move the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position along a first dimension, at block 222 And may include crystals that overturn at least one selected fission fuel sub-assembly (14).

In some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along a second dimension. In some other embodiments, the selected set of dimensional constraints is a function of at least one flame surface criterion. For example, the flame front reference may include a neutron flux such as (but not limited to) a neutron flux associated with at least one selected fission fuel sub-assembly. As another example, the flame surface criterion may include a volumetric neutron flux, such as (but not limited to) a poetic atomic neutron flux associated with at least one selected fission fuel sub-assembly. As another example, the flame front reference may include a degree of combustion such as, but not limited to, the degree of combustion associated with at least one selected fission subsystem 14. In some other embodiments, the flame front reference may include a flame front position within the at least one selected fission fuel sub-assembly.

2I, in some embodiments, at decision block 206, the decision to move the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position along a first dimension is performed at block 224 , A crystal that moves the selected fission fuel sub-assembly (14) radially along a first dimension from a respective first location toward a respective second location. 2J, at decision block 206, a decision to move the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position along a first dimension is performed at block 226 , A crystal that moves the selected fission fuel sub-assemblies (14) helically along a first dimension from a respective first position toward a respective second position. 2K, at decision block 206, a decision to move the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position along a first dimension, At 228, a determination may be made to axially translocate the selected fission subsets 14.

Referring further to Figure 2L, in some embodiments, determining the desired shape of the fission progressive flame front 22 at block 204 includes determining a substantially spherical shape of the fission progressive flame front 22 at block 230 can do. 2M, determining the desired shape of the fission progressive wave flame surface 22 along the second dimension at block 204 may include determining the desired shape of the continuous wave surface 22 of the fission progressive wave flame surface 22 at block 232. In some embodiments, Lt; / RTI > In some other embodiments, the curved surface can be made to increase the surface area of the flame surface. In this embodiment, the leakage of neutrons from the combustion zone to the growth zone is increased.

The preferred shape of the fission progressive wave flame surface 22 may be any shape. As described above, in various embodiments, the preferred shape of the fission progressive flame front 22 may be substantially rotationally symmetric about the second dimension; The preferred shape of the fission progressive flame front 22 may have a substantial n fold rotational symmetry around the second dimension; The preferred shape of the fission progressive flame front 22 may be asymmetric; And / or the preferred shape of the fission progressive flame front 22 may be rotationally asymmetric around the second dimension. In some other embodiments, the symmetric shape of the n-fold symmetry can be converted into a separate combustion zone within the nuclear fission wave reactor core. For example, the flame side can be converted into a lobe that can be further propagated to n or fewer separate (i.e., neutronically separated) combustion regions (see FIG. 1V).

Some embodiments may be provided as an exemplary system. By way of example, and referring now to FIG. 3A, an exemplary system 300 for determining movement of a fissile fuel subassembly (not shown in FIG. 3A) is provided. As a non-limiting example, the provided system 300 may provide a suitable system environment for performing the method 200 (FIGS. 2A-2M). 1B, for a fission progressive wave flame front 22 propagating along the first and second dimensions, the electrical circuit 302 is positioned within the fission fuel sub- And to determine the desired shape of the fission propagating fire flame surface 22 along the dimensions according to the selected set of dimensional constraints. The electrical circuitry 304 is configured to determine the movement of the selected fission fuel sub-body 14 in a manner responsive to a desired shape from a first position to a respective second position according to a first dimension.

In general, those skilled in the relevant art will appreciate that the various aspects described herein may be implemented individually and / or collectively by a wide variety of hardware, software, firmware, and / or any combination thereof, &Quot; as < / RTI > Thus, " electrical circuit " as used herein includes, but is not limited to, an electrical circuit having at least one discrete electrical circuit, an electrical circuit having at least one integrated circuit, an electrical circuit having at least one special purpose integrated circuit Circuitry, a general purpose computer configured by a computer program that at least partially accomplishes the processes and / or devices described herein, or a process and / or device described herein, An electrical circuit forming a memory device (e.g., memory (e.g., RAM, flash memory, ROM, etc.)), and / And an electrical circuit forming a device (e.g., modem, communication switch, photoelectric device, etc.). Those of skill in the relevant art will recognize that the subject matter described herein may be implemented in analog or digital fashion, or some combination thereof.

3B, in an exemplary embodiment, electrical circuitry 302 and / or electrical circuitry 304 may be embodied as a computing system 306 (also referred to as a host computer or system). In an exemplary embodiment, a central processing unit (" CPU ") (or microprocessor) 308 is connected to the system bus 310. A random access main memory (" RAM ") 312 is coupled to the system bus 310 to provide access to the memory storage 314 to the CPU 308, May be used to store data associated with one or more parameters). When executing a program command, the CPU 308 stores these processing steps in the RAM 312 and reads and executes the stored processing steps from the RAM 312. [

Computing system 306 may be connected to a computer network (not shown) via network interface 316 and through a network connection (not shown). One such network is the Internet, which allows the computing system 306 to download applications, code, documents, and other electronic information.

A read only memory (" ROM ") 318 is provided for storing an invariant command sequence, such as a start command sequence or a basic input / output operating system (BIOS) sequence.

The input / output (" I / O ") device interface 320 provides a means for the computing system 306 to access various input / output devices such as keyboards, pointing devices Let's do it. The I / O device interface 320 is shown as a single block for simplicity and may include several interfaces for interfacing with other types of I / O devices.

It will be appreciated that the embodiment is not limited to the architecture of the computing system 306 shown in FIG. 3B. Depending on the type of application / business environment, the computing system 306 may have more or fewer components. For example, the computing system 306 may be a set-top box, a laptop computer, a notebook computer, a desktop computer, or other type of system.

In various embodiments, some of the systems and methods of the present invention may include one or more computer program products. The computer program product includes computer readable storage medium, such as a non-volatile storage medium, computer readable program code, such as a series of computer instructions stored in a computer readable storage medium. Typically, a computer program is stored and executed by a processing device or associated memory device, such as, for example, the processing components shown in FIG. 3B.

In this regard, Figures 2A-2M and Figures 3A-3C show flowcharts and block diagrams of methods, systems, and program products, respectively, in accordance with various embodiments. It will be appreciated that each block of the flowchart and block diagrams, and combinations of blocks in the flowcharts and block diagrams, may be implemented by computer program instructions. Such computer program instructions may be loaded into a computer or other programmable device so that the instructions executing on the computer or other programmable device may constitute a machine that causes the flow diagram or block diagrammed means to implement the functions. Such computer program instructions may also be stored in a computer-readable memory that directs the computer or other programmable apparatus to function in a special manner so that the instructions stored in the computer-readable memory include instructions for implementing the flowchart or block- To produce an article of manufacture. Computer program instructions may also be loaded into a computer or other programmable device so that a series of operational steps may be performed on the computer or other programmable device so that the instructions executing on the computer or other programmable device implement the flowchart or block- To provide the steps that are to be performed.

Therefore, each block of the flowchart or block diagram supports a combination of means for performing a particular function, a combination of steps for performing a particular function, and program instruction means for performing a particular function. A combination of blocks in each block and flow diagram or block diagram of the flowchart or block diagram may be implemented by a special purpose hardware based computer system that performs a particular function or step or by a combination of special purpose hardware and computer instructions I will also understand.

Referring to Figure 3C, in some embodiments, electrical circuit 304 may also be configured to determine an existing shape of the fission progressive wave flame surface 22. For example, the sensors 322 may be operatively coupled to the electrical circuit 304 via a suitable input interface 324 during signal communication. The sensors 322 may comprise any suitable sensor that measures the parameters of the fission progressive wave flame surface 22. For example, the sensors 322 can measure neutron flux, momentum neutron flux, burnup, and / or reactivity (or any of these components).

As described above, embodiments of the system 300 and the electrical circuits 302 and 304 may be implemented in a computer or other programmable apparatus, whether or not a computer program instruction is loaded into a computer or other programmable apparatus comprising the machine, In a flowchart or block diagram, or in a block diagram or a block diagram or block diagram of a flowchart or block diagram, in which the instructions executing on the computer are implemented by a special purpose hardware-based computer system or a combination of special purpose hardware and computer instructions that perform particular functions or steps And to provide a suitable system environment for performing the method 200 (Figs. 2A-2M) to create a means for implementing the specified function in combination with each block. Some features of various embodiments of the system 300 will be described with additional reference to Figures 1B to 1D, 1J, 1L, 10, 1Q, 1R to 1W, and 2A to 2M.

To this end, in some embodiments, the electrical circuitry 304 is configured to move the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position in a manner that establishes the desired shape ≪ / RTI > The electrical circuit 304 may also be configured to make a decision to move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that maintains the desired shape. The electrical circuitry 304 may also be configured to determine when to move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner responsive to a desired shape have.

As noted above, in some embodiments, the fission fuel sub-assembly 14 may extend along a second dimension.

As also noted above, in some embodiments, the first dimension may be substantially orthogonal to the long axis of the fission fuel sub-assembly 14. [ In some other embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

In various embodiments, the first dimension comprises a radial dimension and the second dimension comprises an axial dimension; Wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension; The first dimension comprises an axial dimension and the second dimension comprises a lateral dimension; And / or the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

In some embodiments, the first position may include an outer position 30 and the second position may comprise an inner position 32. In some embodiments, The inner and outer locations 32 and 30 may have various desirable properties such as geometric proximity to the center of the reactor core 12 and the geometric proximity of the neutron beam at the inner location 32 to the neutron flux at the outer location 30. [ so that a larger (but not limited to) the _effective k from the neutron flux, and / or inner position 32, so that a larger reactivity than in the _effective k from the outer position 30 can be determined according to.

In some other embodiments, the first position may include an inner position 32 and the second position may comprise an outer position 30. [ The inner and outer locations 32 and 30 may have various desirable properties such as geometric proximity to the center of the reactor core 12 and the geometric proximity of the neutron beam at the inner location 32 to the neutron flux at the outer location 30. [ so that a larger (but not limited to) the _effective k from the neutron flux, and / or inner position 32, so that a larger reactivity than in the _effective k from the outer position 30 can be determined according to. In some embodiments, the first position and the second position may be located on both sides of the reference value along the first dimension.

In some other embodiments, the first location and the second location may include at least one attribute that is substantially equivalent. For example, at least one attribute may include geometric proximity to the central region of the reactor core 12, neutron flux, and / or reactivity.

In some embodiments, the electrical circuitry 304 may be configured to make a decision to rotate at least one selected fission fuel subcollector 14. In some other embodiments, the electrical circuit 304 may also be configured to make a decision to flip the at least one selected fission subsystem 14.

As described above, in some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along the second dimension.

In some other embodiments, the selected set of dimensional constraints may be a function of at least one flame surface reference. For example, the flame front reference may include, but is not limited to, a neutron flux, such as a neutron flux, associated with at least one selected fission fuel sub-assembly 14; Poetic atomic neutrals such as poetic atomic neutrals associated with at least one selected fission fuel sub-assembly (14); And / or a degree of combustion such as a combustion rate associated with at least one selected fission fuel sub-assembly 14. [ In some embodiments, the flame surface reference may include a flame surface position in at least one selected fission fuel sub-assembly.

In some embodiments, the electrical circuitry 304 can also be configured to make a decision to radially move the selected fission subsets 14 from their respective first positions toward their respective second positions along a first dimension have. The electrical circuitry 304 may also be configured to make a decision to move the selected fission fuel sub-assemblies 14 spirally along a first dimension from a respective first location toward respective second locations. The electrical circuit 304 may also be configured to make a decision to cause the selected fission fuel subcollector 14 to be converted axially.

In some embodiments, the electrical circuit 302 may also be configured to determine the shape of the fission track wave flame surface 22 that is substantially spherical. The electrical circuit 302 may also be configured to determine the shape of the fission progressive wave flame surface 22, which is a continuous curved shape.

In various embodiments, the preferred shape of the fission traveling wave flame surface 22 may be substantially rotationally symmetric about the second dimension; May have a substantially n-fold rotational symmetry around the second dimension; And / or asymmetrical to be rotationally asymmetric around the second dimension (but not limited to).

As another example, referring now to FIG. 4A, another exemplary system 400 for moving a fissile fuel subassembly (not shown in FIG. 4A) is provided. As a non-limiting example, the provided system 400 may provide a suitable system environment for performing the method 100 (FIGS. 1A-1AF). Therefore, the following description is made with reference to Figs. 1A to 1 IA.

In some embodiments, for a fission traveling wave flame front 22 propagating along the first and second dimensions, the electrical circuit 402 includes a fission progressive flame side (not shown) along the second dimension in the fission fuel sub- And to determine the preferred shape of the second set of dimensions 22 according to the selected set of dimensional constraints. The electrical circuitry 404 is configured to determine the movement of the selected fission fuel sub-body 14 in a manner responsive to a desired shape from a first position to a respective second position according to a first dimension. The subassembly 405 is configured to move the selected fission fuel subcollector 14 in response to the electrical circuitry 404.

It will be appreciated that the electrical circuits 402 and 404 may be similar to the electrical circuits 302 and 304. In some cases, the electrical circuits 402 and 404 may be identical to the electrical circuits 302 and 304. For this reason and for the sake of simplicity, it will not be necessary to repeat the details for the sake of understanding.

4B, in an exemplary embodiment, electrical circuit 402 and / or electrical circuit 404 may be embodied as a computing system 406 (also referred to as a host computer or system). In an exemplary embodiment, a central processing unit (" CPU ") (or microprocessor) 408 is connected to the system bus 410. A random access main memory (" RAM ") 412 is coupled to the system bus 410 to provide access to the memory storage 414 to the CPU 408, May be used to store data associated with one or more parameters). When executing a program command, the CPU 408 stores these processing steps in the RAM 412 and reads and executes the stored processing steps from the RAM 412. Computing system 406 may be connected to a computer network (not shown) via network interface 416 and through a network connection (not shown). A read only memory (" ROM ") 418 is provided for storing an immutable command sequence, such as a start command sequence or a basic input / output operating system (BIOS) sequence. The input / output (" I / O ") device interface 420 may be used by the computing system 406 to access various input / output devices such as keyboards, pointing devices Let's do it. It will be appreciated that the embodiment is not limited to the architecture of the computing system 406 shown in FIG. 4B. A non-limiting description of the computing system 306 (FIG. 3B) also applies to the computing system 406. FIG.

In various embodiments, some of the systems and methods of the present invention include one or more computer program products. The above description of a computer program product related to the system 300 (FIG. 3A) also applies to the system 400. FIG.

In this regard, FIGS. 1A, 1I, 1K, 1M to 1N, 1P, 1X to 1AF, and 4A to 4C show flowcharts and block diagrams of methods, systems, and program products, respectively, in accordance with various embodiments. It will be appreciated that each block of the flowchart and block diagrams, and combinations of blocks in the flowcharts and block diagrams, may be implemented by computer program instructions. Such computer program instructions may be loaded into a computer or other programmable device so that the instructions executing on the computer or other programmable device may constitute a machine that causes the flow diagram or block diagrammed means to implement the functions. Such computer program instructions may also be stored in a computer-readable memory that directs the computer or other programmable apparatus to function in a special manner so that the instructions stored in the computer-readable memory include instructions for implementing the flowchart or block- To produce an article of manufacture. Computer program instructions may also be loaded into a computer or other programmable device so that a series of operational steps may be performed on the computer or other programmable device so that the instructions executing on the computer or other programmable device implement the flowchart or block- To provide the steps that are to be performed.

Therefore, each block of the flowchart or block diagram supports a combination of means for performing a particular function, a combination of steps for performing a particular function, and program instruction means for performing a particular function. A combination of blocks in each block and flow diagram or block diagram of the flowchart or block diagram may be implemented by a special purpose hardware based computer system that performs a particular function or step or by a combination of special purpose hardware and computer instructions I will also understand.

Referring to Figure 4C, in some embodiments, the electrical circuit 404 may also be configured to determine an existing shape of the fission progressive wave flame surface 22. For example, the sensors 422 may be operatively coupled to the electrical circuit 404 via an appropriate input interface 424 during signal communication. The electrical circuit 404, the sensor 422 and the input interface 424 may be similar to the electrical circuit 304, the sensor 322 and the input interface 324 (all shown in Figure 3C) Can be the same). You will not need to repeat their details in order to understand.

As described above, embodiments of the system 400, the electrical circuits 402 and 404, and the subsystem 405 may be implemented in any computer system, including, but not limited to, Flowcharts or block diagrams in which instructions executing on a computer or other programmable device are implemented by a special purpose hardware-based computer system that performs particular functions or steps or by a combination of special purpose hardware and computer instructions, (FIGS. 1A, 1I, 1K, 1M to 1N, 1P, and 1X to 1AF) to create a means for implementing a function specified in each block and a combination of blocks in the flowchart or block diagram Lt; RTI ID = 0.0 > and / or < / RTI > Some features of various embodiments of the system 400 will be described with additional reference to Figures 1A-1F.

In some embodiments, referring to FIG. 4C, the electrical circuit 404 may also be configured to determine an existing shape of the fission progressive wave flame surface 22. This determination can be made in a manner similar or identical to that of the electrical circuit 304 (FIG. 3A) described above. Sensor 422 and input interface 424 are similar or in some cases identical to sensor 322 and input interface 324 (both shown in Figure 3C). Sensor 422, input interface 424 and electrical circuit 404 cooperate as described above for sensor 322, input interface 324 and electrical circuit 304 (all shown in FIG. 3C).

In some embodiments, the electrical circuitry 404 may be configured to make a decision to move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that establishes the desired shape It can also be configured. In some alternative embodiments, the electrical circuitry 404 may include a determination to move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that maintains the desired shape . ≪ / RTI >

In some embodiments, the electrical circuitry 404 is configured to move the selected fissionable fuel sub-assembly 14 from its respective first position to its respective second position in a manner responsive to a desired shape, And < / RTI >

In some embodiments, the fission fuel sub-assembly 14 may extend along a second dimension. The first dimension may be substantially orthogonal to the long axis of the fission fuel sub-assembly 14. The first dimension and the second dimension may be substantially orthogonal to each other.

In various embodiments, the first dimension comprises a radial dimension and the second dimension comprises an axial dimension; Wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension; The first dimension comprises an axial dimension and the second dimension comprises a lateral dimension; And / or the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

In some embodiments, the first position may include an outer position 30 and the second position may comprise an inner position 32. In some embodiments, The inner and outer locations 32 and 30 are designed to have a geometric proximity to the center of the reactor core 12 such that the neutron flux at the inner location 32 is greater than the neutron flux at the outer location 30, And / or the k _effective at the inner position 32 is greater than k _effective at the outer position 30. [

In some other embodiments, the first position may include an inner position 32 and the second position may comprise an outer position 30. [ The inner and outer positions are selected such that the geometric proximity to the center of the reactor core 12, the neutron flux at the inner position 32 is greater than the neutron flux at the outer position 30, and / ) is _effective k it can be determined according to the reactivity to be larger than the _effective k from the outer position 30 of the.

In some embodiments, the first position and the second position may be located on both sides of the reference value along the first dimension.

In some other embodiments, the first location and the second location may include at least one attribute that is substantially equivalent. For example, at least one attribute may include geometric proximity to the central region of the reactor core 12, neutron flux, and / or reactivity.

In various embodiments, the electrical circuit 404 may be configured to make a decision to rotate at least one selected fission fuel subcollector 14. The electrical circuit 404 may also be configured to make a decision to flip the at least one selected fission subsystem 14.

Subassembly 405 may include any suitable fuel handling device known in the art, such as, but not limited to, a nuclear fuel handling device. However, in some other embodiments, subassembly 405 may include an extra-core fuel handling device.

Regardless of the form in which the subassembly 405 is embodied, in various embodiments, the subassembly 405 moves the selected fission fuel subassembly 14 radially from its respective first position to its respective second position As shown in FIG. The subassembly 405 may also be configured to spiral the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position. Subassembly 405 may also be configured to axially convert the selected fissile fuel subassembly.

In some embodiments, the subassembly 405 may also be configured to rotate the selected fission fuel sub-assembly 14. In some other embodiments, the subassembly 405 may also be configured to flip the selected fission fuel sub-assembly 14. Referring now to FIG. 5, in various embodiments, an exemplary fission progressive wave reactor 500 is provided. The fission progressive wave reactor 500 includes a fission progressive wave reactor core 12. As described above, the fission fuel sub-assembly 14 is accommodated in a nuclear fission traveling wave reactor core 12. [ Each fission fuel sub-assembly 14 is configured to propagate the fission progressive fire plane 22 therein along the first and second dimensions. The electrical circuit 402 is configured to determine the desired shape of the fission progressive wave flame surface 22 along the second dimension within the fissile fuel subassembly 14 according to the selected set of dimensional constraints. The electrical circuit 404 is configured to determine the movement of the selected fission fuel sub-body 14 along the first dimension from each first position to each second position in a manner responsive to a desired shape. The subassembly 405 is configured to move the selected fission fuel subcollector 14 in response to the electrical circuitry 404.

Thus, the reactor 500 can be embodied as the reactor core 12 described above, in conjunction with the system 400 and with the system 400 described above. The reactor core 12 (and its components) and the system 400 (and its components) have been described in detail above, so that the details will not need to be repeated for the sake of understanding.

As described above, in various embodiments, the electrical circuit 404 may also be configured to determine an existing shape of the fission progressive wave flame surface 22. The electrical circuit 404 may also be configured to make a determination to move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that establishes the desired shape. The electrical circuit 404 may also be configured to make a decision to move the selected fission fuel sub-assembly 14 along the first dimension from each first position toward each second position in a manner that maintains the desired shape.

As noted above, in some embodiments, the electrical circuitry 404 is configured to move the selected fission fuel sub-bodies 14 from their respective first positions toward their respective second positions in a manner that responds to a desired shape along a first dimension May also be configured to determine when to move.

In some embodiments, the fission fuel sub-assembly 14 may extend along a second dimension.

In some embodiments, the first dimension may be substantially orthogonal to the long axis of the fission fuel sub-assembly 14. In some embodiments, the first dimension and the second dimension may be substantially orthogonal to each other.

In various embodiments, the first dimension comprises a radial dimension and the second dimension comprises an axial dimension; Wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension; The first dimension comprises an axial dimension and the second dimension comprises a lateral dimension; And / or the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

In some embodiments, the first position may include an outer position 30 and the second position may comprise an inner position 32. In some embodiments, The inner and outer locations 32 and 30 are designed to have a geometric proximity to the center of the reactor core 12 such that the neutron flux at the inner location 32 is greater than the neutron flux at the outer location 30, And / or the k _effective at the inner position 32 is greater than k _effective at the outer position 30. [

In some other embodiments, the first position may include an inner position 32 and the second position may comprise an outer position 30. [ The inner and outer locations 32 and 30 are designed to have a geometric proximity to the center of the reactor core 12 such that the neutron flux at the inner location 32 is greater than the neutron flux at the outer location 30, And / or the k _effective at the inner position 32 is greater than k _effective at the outer position 30. [

In some embodiments, the first position and the second position may be located on both sides of the reference value along the first dimension.

In some embodiments, the first location and the second location may include at least one attribute that is substantially equivalent. The at least one property may include geometric proximity to the central region of the reactor core 12, neutron flux, and / or reactivity.

In various embodiments, as described above, the electrical circuit 404 is configured to make a decision to rotate at least one selected fission fuel subcollector 14 and / or at least one selected fission fuel subcollector 14 It can also be configured to make a reversing decision.

In some embodiments, the selected set of dimensional constraints may include a predetermined maximum distance along a second dimension. In some other embodiments, the selected set of dimensional constraints includes, for example and without limitation, a neutron flux, such as a neutron flux, associated with at least one selected fission fuel sub-assembly 14; Poetic atomic neutrals such as poetic atomic neutrals associated with at least one selected fission fuel sub-assembly (14); And / or at least one flame surface criterion, such as a flammability degree associated with at least one selected fission fuel sub-assembly 14. In some other embodiments, the flame front reference may include a flame front position within the at least one selected fission fuel sub-assembly.

In various embodiments, the electrical circuitry 404 can also be configured to make a decision to radially move the selected fission subsets 14 from their respective first positions toward their respective second positions along a first dimension have. The electrical circuit 404 may also be configured to make a decision to move the selected fission fuel sub-assembly 14 spirally along the first dimension from each first location toward each second location. The electrical circuit 404 may also be configured to make a decision to cause the selected fission fuel subcollector 14 to be axially transformed.

In various embodiments, the electrical circuit 402 may also be configured to determine the shape of a fission track wave flame surface 22 that is substantially spherical, and / or a fission track wave flame surface 22 that is a continuous curve shape. The preferred shape of the fission progressive flame front 22 may be substantially rotationally symmetric about the second dimension; May have a substantially n-fold rotational symmetry around the second dimension; And / or asymmetric about the second dimension, such as rotationally asymmetric.

In some embodiments, subassembly 405 may include a nuclear fuel handling device. As discussed above, the subassembly 405 may include any suitable fuel handling device known in the art, such as, but not limited to, a nuclear fuel handling device. However, in some other embodiments, subassembly 405 may include a non-core fuel handling device.

As described above, in various embodiments, the subassembly 405 may also be configured to radially move the selected fission fuel sub-assembly 14 from its respective first position to its respective second position. The subassembly 405 may also be configured to spiral the selected fission fuel sub-assembly 14 from its respective first position toward its respective second position. Subassembly 405 may also be configured to axially convert the selected fissile fuel subassembly. The subassembly 405 may also be configured to rotate the selected fission fuel subcollector 14. The subassembly 405 may also be configured to flip the selected fission fuel subcollector 14.

Referring now to FIG. 6A, in some embodiments, a method 600 for operating a fission traveling wave reactor is provided. The method 600 begins at block 602. With reference to FIG. 1B, at block 604, at least one fission fuel assembly 14 is moved outward from a first position of the fission traveling wave reactor core 12 to a second position of the fission traveling wave reactor core 12. The method 600 ends at block 606.

In some embodiments, referring to FIG. 6B, at block 608, at least one fission fuel assembly 14 may be moved inward from a second position.

In various embodiments, the first and second locations are geometric proximity to the center of the reactor core 12; A neutron flux so that the neutron flux at the first location is larger than the neutron flux at the second location; And k _effective at the first position is greater than k _effective at the second position.

Referring now to FIG. 7, in some embodiments, a method 700 for operating a fission progressive nuclear reactor is provided. The method 700 begins at block 702. 1B, at block 704, at least one fission fuel assembly 14 is moved in a first direction from a first location on a nuclear fission traveling wave reactor core 12 to a second location on a nuclear fission traveling nuclear reactor core 12 . The second position is different from the first position. At block 706, it is determined to move the at least one fission fuel assembly 14 from the second position in the second direction. The second direction is different from the first direction. The method 700 ends at block 708.

In some embodiments, the first direction may be an outward direction and the second direction may be an inward direction. The first and second locations may include various attributes or parameters, such as geometric proximity to the center of the reactor core 12; A neutron flux so that the neutron flux at the first location is larger than the neutron flux at the second location; And / or such that k _effective at the first location is greater than k _effective at the second location.

In some other embodiments, the first direction may be an inward direction and the second direction may be an outward direction. The second position and the first position may include various attributes or parameters, such as geometric proximity to the center of the reactor core 12; A neutron flux such that the neutron flux at the second location is larger than the neutron flux at the first location; And / or such that k _effective at the second location is greater than k _effective at the first location.

Referring now to FIG. 8, in some embodiments, a method 800 for operating a fission traveling wave reactor is provided. The method 800 begins at block 802. 1B, at block 804, at least one fission fuel assembly 14 is moved from a first location on the fission progress wave reactor core 12 to a second location on the fission progress wave reactor core 12 in a first direction do. The second position is different from the first position. At block 806, it is determined to move the at least one fission fuel assembly 14 from the second position in the second direction. The second direction is different from the first direction. The method 800 ends at block 808.

In some embodiments, the first direction may be an outward direction and the second direction may be an inward direction. The first and second locations may include various attributes or parameters, such as geometric proximity to the center of the reactor core 12; A neutron flux so that the neutron flux at the first location is larger than the neutron flux at the second location; And / or such that k _effective at the first location is greater than k _effective at the second location.

In some other embodiments, the first direction may be an inward direction and the second direction may be an outward direction. The second position and the first position may include various attributes or parameters, such as geometric proximity to the center of the reactor core 12; A neutron flux such that the neutron flux at the second location is larger than the neutron flux at the first location; And / or such that k _effective at the second location is greater than k _effective at the first location.

Referring now to FIG. 9, in some embodiments, a method 900 for operating a fission traveling wave reactor is provided. The method 900 begins at block 902. 1B, at block 904, at least one fission fuel assembly 14 is moved in a first direction from a first location on a nuclear fission traveling wave reactor core 12 to a second location on a nuclear fission traveling wave reactor core 12, do. The second position is different from the first position. At block 906, at least one fission fuel assembly 14 is moved in a second direction from a second position. The second direction is different from the first direction. The method 900 ends at block 908.

In some embodiments, the first direction may be an outward direction and the second direction may be an inward direction. The first and second locations may include various attributes or parameters, such as geometric proximity to the center of the reactor core 12; A neutron flux so that the neutron flux at the first location is larger than the neutron flux at the second location; And / or such that k _effective at the first location is greater than k _effective at the second location.

In some other embodiments, the first direction may be an inward direction and the second direction may be an outward direction. The second position and the first position may include various attributes or parameters, such as geometric proximity to the center of the reactor core 12; A neutron flux such that the neutron flux at the second location is larger than the neutron flux at the first location; And / or such that k _effective at the second location is greater than k _effective at the first location.

Referring now to FIG. 10A, in some embodiments, a method 1000 for operating a fission reactor is provided. The method 1000 begins at block 1002. A predetermined burnup level is selected at block 1004. At block 1006, it is determined to move the selected fission fuels aggregate in the fission reactor core to a manner that achieves an equivalent burnup level towards a predetermined firing level of substantially all fission fuel assemblies. The method 1000 ends at block 1008.

Referring to FIG. 10B, in some embodiments, at block 1010, the selected fission fuels aggregate may be moved in the fission reactor core in a manner responsive to the moving crystals.

Referring to FIG. 10C, in some embodiments, at block 1012, the removal of each selected fission fuel bundle may be determined when the burnup level is equalized toward a predetermined burnup level.

Referring to FIG. 10D, in some embodiments, at block 1014, the selected fission fuels aggregate may be removed in response to the removal determination.

We use formal abstract headings for clarity of expression. However, it should be understood that the outline title is for presentation purposes and that other types of topics may be discussed throughout the specification (e.g., the device / structure may be described under the process / action heading, and / May be discussed under the structure / process heading, and / or the description of a single topic may span more than one topic heading). Therefore, the use of formal abstract headings is not intended to be limiting in any way.

Those skilled in the relevant art will appreciate that the specific exemplary processes and / or devices and / or techniques described above may be practiced elsewhere herein, such as in the claims submitted together and / or in the more general process and / Or devices and / or techniques described herein.

Those skilled in the relevant art (s) have advanced to the point where the state of the art is not substantially different between hardware implementations, software implementations, and / or firmware implementations of the system aspects, and the use of hardware, software and / However, you will recognize that in some situations it is not always the case that the choice between hardware and software can be significant. (E. G., Hardware, software, and / or firmware) in which the processes and / or systems and / or other techniques described herein may be practiced if one of ordinary skill in the relevant art / RTI > and / or < / RTI > system and / or other technologies are developed. For example, if the implementer determines that speed and accuracy are the most important, the implementer can chose mainly the hardware and / or firmware medium and, alternatively, if flexibility is most important, the implementer can chose mainly the software implementation, or Alternatively, the implementer may select any combination of hardware, software, and / or firmware. Therefore, there are several possible medias that can implement the processes and / or devices and / or other techniques described herein, and that the choice of mediators depending on the circumstances in which they are developed and the particular attention of the implementer (e.g., speed, flexibility or predictability) In terms of specification, a medium is not inherently superior to other mediums, and the options may vary. Those skilled in the relevant art will recognize that the optical aspects of the implementations will typically use optical-oriented hardware, software and / or firmware.

In some implementations described herein, logical and similar implementations may include software or other control structures. For example, an electronic circuit may have one or more current paths configured and arranged to implement the various functions described herein.

Alternatively or additionally, an implementation may include circuitry that enables, commences, adjusts, requests, or otherwise causes the execution of a special purpose instruction sequence or one or more occurrences of substantially any functional operation described herein ≪ / RTI > In some variations, the operational or other logical description herein may be expressed as source code, compiled as a sequence of executable instructions, or otherwise called. In some situations, for example, an implementation may be provided, in whole or in part, by source code, such as C ++, or by another code sequence. In other implementations, source code or other code implementations using commercially available and / or techniques known in the art may be compiled / implemented / translated / translated into advanced descriptors (see, for example, Hardware descriptions language implementations, hardware design simulation implementations, and / or other similar representation modes), as described above, in a C or C ++ programming language, and then translating the programming language implementation into a logically synthesizable language implementation. For example, some or all of the logical representations (e.g., computer programming language implementations) may be implemented in a verilog type hardware technology (e.g., via a hardware description language (HDL) and / or a high speed integrated circuit hardware description language (VHDL) (E.g., a special purpose integrated circuit) that can be used to generate a physical implementation having a plurality of memory cells. Those skilled in the relevant art will recognize how to obtain, configure and optimize appropriate transmission or computation elements, material supply, actuators or other structures in light of the teachings herein.

The foregoing detailed description has described various embodiments of the apparatus and / or process through block diagrams, flow charts and / or examples. It is to be understood that each block and / or feature in the block diagrams, flowcharts, and / or examples may be implemented in a wide variety of hardware, software, firmware, It will be understood by those skilled in the art that the present invention can be implemented individually and / or collectively by any combination of these. In one embodiment, some portions of the subject matter described herein may be implemented through special purpose integrated circuits (ASICs), field programmable gate arrays (FPGAs), digital signal processors (DSPs), or other integrated formats. However, those of skill in the relevant art will appreciate that some aspects of the embodiments described herein may be embodied as one or more computer programs (e.g., one or more programs running on one or more computer systems) operating in whole or in part on one or more computers, May be equivalently implemented in an integrated circuit as one or more programs running on one or more processors (e.g., one or more programs running on one or more microprocessors), as firmware, or substantially any combination thereof, And code design for circuitry and / or software and / or firmware are within the knowledge of one of ordinary skill in the art in light of this specification. It will also be appreciated by those skilled in the art that the subject matter described herein may be distributed as a variety of types of program products and that the exemplary embodiments of the subject matter described herein may be embodied with special signal transport But will apply regardless of the media type. Examples of signal carrying media include, but are not limited to, recordable media such as floppy disks, hard disk drives, compact discs (CDs), digital video disks (DVDs), digital tapes,

In general, those skilled in the relevant art will recognize that the various embodiments described herein may be practiced with a wide variety of electrical components, such as hardware, software, firmware, and / or a combination thereof; And / or by various types of electromechanical systems having a wide variety of components capable of imparting mechanical force or motion, such as a rigid body, a spring or torsion body, a hydraulic device, an electromagnetic drive, and / Or may be implemented in a comprehensive manner. Thus, " electromechanical system " as used herein includes, but is not limited to, an electrical circuit operatively coupled to a transducer (e.g., an actuator, a motor, a piezoelectric crystal, a microelectromechanical system An electrical circuit having at least one integrated circuit, an electrical circuit having at least one special purpose integrated circuit, a general purpose computing device configured by a computer program (e.g., A microprocessor configured by a general purpose computer configured by a computer program that at least partially accomplishes the device, and / or a computer program that at least partially accomplishes the process and / or apparatus described herein), a memory (E. G., Memory (e. G., RAM, flash memory, ROM, etc.) As, a communication device, an electronic circuit which forms the (e. G., A modem, communications switch, optical devices, etc.), and / or non-electrical (非 電氣) analogues, such as optical or other analogs. Those skilled in the relevant art will appreciate that examples of electromechanical systems include, but are not limited to, various consumer electronics systems, medical equipment, as well as a motorized transportation system, a factory automation system, a security system, and / ≪ / RTI > Those of skill in the relevant art will recognize that the electromechanical instrument used herein is not necessarily limited to a system having both electrical and mechanical actions, unless the context indicates otherwise.

All of the foregoing US patents, US patent application publications, US patent applications, foreign patents, foreign patent applications, and non-patent publications cited in this specification and / or listed in any application data sheet are herein incorporated by reference to the extent not inconsistent Which is incorporated herein by reference.

Those skilled in the relevant art will recognize that the components (e.g., operations), apparatuses, objects, and attendant descriptions described herein are used as examples for conceptual clarification and that various configuration changes are contemplated something to do. As a result, as used herein, the specific embodiments described and the accompanying discussion are intended as representative examples of the more general classes. In general, the use of any particular example herein is also intended to be representative of that class, and the absence of such specific elements (e.g., operation), apparatus, and objects herein should not be construed as limiting.

With regard to the use of substantially any plural and / or singular terms herein, those skilled in the relevant art (s) may interpret plural forms singly and / or singular forms plural, as appropriate for the context and / or use. For the sake of brevity, various singular / plural substitutions are not explicitly set herein.

The subject matter described herein sometimes describes other components that are included in other components or that are connected to other components. It is to be understood that such a structure is merely illustrative and that many other structures may be implemented to achieve the same function in fact. Conceptually, any configuration of components that achieve the same functionality is effectively " related " to achieve the desired functionality. Thus, any two components herein combined to achieve a particular function may be said to be " related " to one another to achieve a desired function. Likewise, any two components associated therewith may also be shown to be " operatively connected " or " operatively coupled " to one another to achieve a desired function, and any two It is also contemplated that the two components may be " operably coupled " to one another to achieve a desired function. Certain embodiments that can be operatively coupled include, but are not limited to, physically-paired and / or physically-interacting components, and / or components that can interact wirelessly and / And / or logically interacting and / or logically interacting components, and the like.

Although specific embodiments of the subject matter described herein have been shown and described, those skilled in the art will appreciate that changes and modifications may be made without departing from the subject matter described herein, and the broader aspects, It is to be understood that the appended claims are intended to cover all such modifications and changes as fall within the true spirit and scope of the subject matter described herein. In general, those skilled in the relevant art will appreciate that the terms used herein, particularly those used in the appended claims (eg, the appended claims), are intended to be broadly intended as "open" terms. (E.g., the term "comprising" should be interpreted as "including but not limited to", and the term "having" should be interpreted as having "at least", and the term "including" Do not "). It will be understood by those skilled in the relevant art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims. For example, for purposes of understanding, the following appended claims are intended to include the use of the phrase " at least one " and " one or more " However, even if the same claim includes an indefinite article such as " one or more " or " at least one " and an " an ", the use of such a phrase is not limited to indefinite article "a" (E.g., " a " and / or " an " is typically to be construed as meaning that any particular claim, including such introduced claim, Quot; at least one " or " at least one "); The same applies to the use of articles of incorporation used to introduce claims. In addition, even if a particular number of the claims recited is expressly stated, those skilled in the art will recognize that such descriptions are usually to be construed as meaning at least the stated number (E.g., " two bases ", which are pure bases without other modifiers, usually means at least two bases, or two or more bases). In addition, when a convention similar to " at least one of A, B, and C, etc. " is used, it is generally understood that such a configuration is understood by those skilled in the relevant art (e.g., A and B together "," A and C together "," B "," B "," C " And C together ", and / or " A and B and C together "). When a convention similar to " at least one of A, B or C " is used, it is generally understood that such a configuration is understood by one skilled in the relevant art (e.g., " A and B together "," A and C together "," B and C "," B "and" C " Together " and / or " A, B and C together "). Typically, separate words and / or phrases expressing two or more alternative terms in any of the detailed description, claims, or drawings in the description, unless otherwise indicated in the context, It will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention. For example, the phrase "A or B" will be understood to include the possibility of "A" or "B" or "A and B".

In the context of the appended claims, those skilled in the relevant art will appreciate that the operations recited herein may be performed in substantially any order. Further, although various operation flows are presented in a predetermined order, various operations may be performed in an order different from the order shown, or may be performed at the same time. Examples of such alternative sequencing may include redundant, intervening, interrupting, reordering, incrementing, reserving, supplementing, concurrent, inverting or other modifying sequences, unless otherwise indicated in the context. Further, terms such as "responding to", "related to", or other past tense adjectives are generally not intended to exclude such variations unless the context requires otherwise.

Aspects of the subject matter described herein are set forth in the following numbered paragraphs.

1. A method of operating a nuclear fission traveling wave reactor,

Propagating a fission progressive flame surface along first and second dimensions in a plurality of fission fuel subassemblies within a reactor core of a fission progressive nuclear reactor;

The selected fissile fuel sub-assemblies from a plurality of fissile fuel sub-assemblies from respective first positions to respective second positions in a manner that defines the shape of the fission progressive flame surface along the second dimension in accordance with the selected dimension constraint set, ≪ / RTI > wherein the method comprises controllably moving along a dimension.

2. The method of clause 1, wherein the plurality of fission fuel sub-assemblies extend along a second dimension.

3. The method of clause 1, wherein the first dimension is substantially orthogonal to the long axis of the plurality of fission fuel sub-assemblies.

4. The method of clause 1, wherein the first dimension and the second dimension are substantially orthogonal to each other.

5. The method of clause 1, wherein the first dimension comprises a radial dimension and the second dimension comprises an axial dimension.

6. The method of clause 1, wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension.

7. The method of clause 1, wherein the first dimension comprises an axial dimension and the second dimension comprises a lateral dimension.

8. The method of clause 1, wherein the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

9. The method of clause 1, wherein the first position comprises an outer position and the second position comprises an inner position.

10. The method of clause 9, wherein the medial and lateral locations are determined by the geometric proximity to the center of the reactor core.

11. The method of clause 9, wherein the medial and lateral positions are determined according to the neutron flux such that the neutron flux at the medial position is larger than the neutron flux at the medial position.

12. The method of clause 9, the inner position and an outer position in a manner _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

13. The method of clause 1, wherein the first position comprises an inner position and the second position comprises an outer position.

14. The method of clause 13, wherein the medial and lateral locations are determined by geometric proximity to the center of the reactor core.

15. The method of clause 13, wherein the inner position and the outer position are determined according to the neutron flux so that the neutron flux at the inner position is larger than the neutron flux at the outer position.

16. In the section 13, the inner position and an outer position in a manner _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

17. The method of clause 1, wherein the first position and the second position are located on both sides of a reference value along the first dimension.

18. The method of clause 1, wherein the first location and the second location comprise at least one property that is substantially equivalent.

19. The method of clause 18, wherein at least one property comprises geometric proximity to a central portion of the reactor core.

20. The method of clause 18, wherein the at least one property comprises a neutron flux.

21. The method of clause 18, wherein at least one attribute comprises reactivity.

22. The method of clause 1, wherein the step of controllably moving selected fissile fuel sub-assemblies of a plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions, along a first dimension, ≪ / RTI > wherein the method further comprises rotating at least one selected fission fuel subassembly.

23. The method of claim 1, wherein the step of controllably moving selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions along a first dimension comprises: Lt; RTI ID = 0.0 > a < / RTI > selected fission fuel sub-assembly.

24. The method of clause 1, wherein the selected set of dimensional constraints comprises a predetermined maximum distance along a second dimension.

25. The method of clause 1, wherein the selected dimensional confinement set is a function of at least one flame surface criterion.

26. In paragraph 25, the flame surface standard includes a neutron flux.

27. The method of 26 wherein the neutron flux is associated with at least one selected fission fuel sub-assembly of a plurality of fission sub-fuel assemblies.

28. In section 25, the flame surface standard includes a poetic atomic neutron flux.

29. The method of 28 wherein the poetic atom neutron is associated with at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

30. The method of clause 25, wherein the flame surface standard includes a degree of combustion.

31. The method of 30 wherein the degree of combustion is associated with at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

32. The method of clause 25, wherein the flame front reference comprises a flame surface position in at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

33. The method of clause 1, wherein the step of controllably moving a selected fissile fuel sub-assembly of a plurality of fissile fuel sub-assemblies from a respective first position to a respective second position along a first dimension comprises: ≪ / RTI > in a radial direction along a first dimension from a respective first location toward a respective second location.

34. The method of clause 1, wherein the step of controllably moving selected fissile fuel sub-assemblies of a plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions along a first dimension comprises: ≪ / RTI > in a helical manner along a first dimension from a respective first position toward a respective second position.

35. The method of clause 1, wherein the step of controllably moving a selected fissile fuel sub-assembly of a plurality of fissile fuel sub-assemblies from a respective first position to a respective second position, according to a first dimension, ≪ / RTI > of the plurality of fissionable fuel sub-assemblies is axially controllable along a first dimension from a respective first position toward a respective second position.

36. The method of clause 1, wherein the shape of the fission propagation flame surface is substantially spherical.

37. The method according to clause 1, wherein the shape of the fission progressive flame surface is substantially coincident with the selected continuous surface.

38. The method of clause 1, wherein the shape of the fission progressive flame surface is substantially rotationally symmetric about the second dimension.

39. The method of clause 1, wherein the shape of the fission progressive flame surface has a substantial n-fold rotational symmetry around the second dimension.

40. The method according to clause 1, wherein the shape of the fission propagation flame surface along the second dimension is asymmetric.

41. The method of 40 wherein the shape of the fission propagation flame surface is rotationally asymmetric about the second dimension.

42. The method of clause 1, further comprising initiating a fission progressive flame side with a plurality of fission progressive wave igniter assemblies.

43. The method of clause 42 wherein, prior to the step of controllably moving selected fissile fuel sub-assemblies of a plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions, ≪ / RTI >

44. The method of clause 43 wherein, prior to the step of controllably moving selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions along a first dimension, Wherein the step of removing at least one of the plurality of fission subsonic fuel subassemblies comprises the step of moving the selected fissile fuel subassemblies from each of the plurality of fission sub- And removing at least one of the assemblies from the second position.

45. The method of clause 1, wherein, prior to the step of controllably moving a selected fissile fuel sub-assembly of a plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions, The method further comprising the step of:

46. The method of paragraph 45 wherein the step of bringing the fission traveling wave reactor into a critical state includes inserting the neutron absorber into the reactor core.

47. The method of paragraph 45, wherein re-establishing the criticality after the step of controllably moving selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies from their respective first locations toward their respective second locations, .

48. The method of 47, wherein the step of re-establishing the threshold comprises removing at least a portion of the neutron absorber material from the reactor core.

49. The method of clause 45 wherein, prior to the step of controllably moving the selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions, Further comprising the step of stopping.

50. The method of clause 49 wherein, after the step of controllably moving the selected fissile fuel sub-assembly out of the plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions along a first dimension, Further comprising steps.

51. A method for controlling a fission traveling wave reactor,

Determining a desired shape of a fission progressive flame surface along a second dimension in a plurality of fission subassemblies for a fission progressive flame front propagating along the first and second dimensions according to a selected set of dimensional constraints;

Determining the movement of the selected fissile fuel sub-assembly among the plurality of fissile fuel sub-assemblies along the first dimension from each first position toward each second position in a manner responsive to a desired shape.

52. In section 51, further comprising the step of determining the existing shape of the fission propagation flame surface.

53. The method of clause 51, wherein the step of determining the movement of the selected fissile fuel sub-assembly among the plurality of fissile fuel sub-assemblies along the first dimension from the respective first position toward the respective second position in a manner responsive to the desired shape And determining the movement of the selected fissile fuel sub-assembly among the plurality of fissile fuel sub-assemblies along the first dimension from each first position toward each second position in a manner that establishes a desired shape.

54. The method of clause 51 wherein the step of determining the movement of a selected fission fuel sub-assembly among a plurality of fission sub-fuel assemblies along a first dimension from a respective first position to respective second positions in a manner responsive to a desired shape Determining the movement of the selected fissile fuel sub-assembly among the plurality of fissile fuel sub-assemblies along the first dimension from each first position toward each second position in a manner that maintains a desired shape.

55. The method of clause 51, wherein a selected fissile fuel sub-assembly of a plurality of fission sub-assemblies is to be moved from a first position to a respective second position along a first dimension in a manner responsive to a desired shape Further comprising steps of:

56. The method of clause 51, further comprising moving the selected fissile fuel sub-assembly among the plurality of fission sub-fuels along the first dimension from each first position toward each second position in a manner responsive to the desired shape Methods of inclusion.

57. The method of 51, wherein the plurality of fission fuel sub-assemblies extend along a second dimension.

58. The method of 51, wherein the first dimension is substantially orthogonal to the long axis of the plurality of fission fuel sub-assemblies.

59. The method of clause 51, wherein the first dimension and the second dimension are substantially orthogonal to each other.

60. The method of 51, wherein the first dimension comprises a radial dimension and the second dimension comprises an axial dimension.

61. The method of clause 51, wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension.

62. The method of 51, wherein the first dimension comprises an axial dimension and the second dimension comprises a lateral dimension.

63. The method of 51, wherein the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

64. The method of clause 51, wherein the first position includes an outer position and the second position includes an inner position.

65. The method of clause 64, wherein the medial and lateral locations are determined by the geometric proximity to the center of the reactor core.

66. The method of clause 64, wherein the medial and lateral positions are determined according to the neutron flux such that the neutron flux at the medial position is larger than the neutron flux at the medial position.

67. In the section 64, the inner position and an outer position in a manner _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

68. The method of 51, wherein the first position includes an inward position and the second position comprises an outward position.

69. The method of clause 68, wherein the inner and outer locations are determined by the geometric proximity to the center of the reactor core.

70. The method of clause 68, wherein the inner and outer positions are determined according to the neutron flux such that the neutron flux at the inner position is larger than the neutron flux at the outer position.

71. In the section 68, the inner position and an outer position in a manner _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

72. The method of clause 51, wherein the first position and the second position are located on both sides of a reference value along the first dimension.

73. The method of 51, wherein the first location and the second location include at least one attribute that is substantially equivalent.

74. The method of 73, wherein at least one attribute comprises geometric proximity to a central portion of the reactor core.

75. The method of 73, wherein at least one attribute comprises a neutron flux.

76. The method of 73, wherein at least one attribute comprises reactivity.

77. The method of clause 51, wherein determining the movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from each first position to a respective second position comprises: And determining rotation of at least one selected fission fuel sub-assembly.

78. The method of clause 51, wherein determining the movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from a respective first position to respective second positions comprises: Determining the flipping of at least one selected fission fuel subassembly.

79. The method of 51, wherein the selected set of dimensional constraints comprises a predetermined maximum distance along a second dimension.

80. The method of 51 wherein the selected set of dimensional constraints is a function of at least one flame surface criterion.

81. In section 80, the flame surface standard includes a neutron flux.

82. The method of 81, wherein the neutron flux is associated with at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

83. In section 80, the flame surface standard includes a poetic atomic neutron flux.

84. The method of 83, wherein the poetic atom neutron is associated with at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

85. In section 80, the flame surface standard includes the degree of flammability.

86. The method of 85 wherein the degree of combustion is associated with at least one selected fission fuel sub-assembly of the plurality of fission fuel sub-assemblies.

87. The method of 80 wherein the flame front reference comprises flame surface position in at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

88. The method of clause 51 wherein determining the movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from each first position to respective second positions comprises: Determining to move the selected fission fuel subassembly in a radial direction along a first dimension from a respective first position toward a respective second position.

89. The method of clause 51 wherein determining the movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from a respective first position to respective second positions comprises: Determining to move the selected fission fuel subassembly helically along a first dimension from a respective first position toward a respective second position.

90. The method of clause 51 wherein determining the movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from each first position to a respective second position comprises: And determining to convert the selected fission fuel sub-assembly into an axial direction.

91. The method of clause 51, wherein determining the desired shape of the fission progressive flame surface comprises determining a substantially spherical shape of the fission progressive flame surface.

92. The method of 51 wherein the step of determining a preferred shape of the fission progressive flame surface along the second dimension comprises determining the shape of the continuous curved surface of the fission progressive flame surface.

93. The method of 51, wherein the desired shape of the fission propagation flame surface is substantially rotationally symmetric about the second dimension.

94. The method of 51 wherein the preferred shape of the fission progressive flame surface has a substantial n-fold rotational symmetry around the second dimension.

95. The method of 51 wherein the preferred shape of the fission propagation flame surface is asymmetric.

96. The method of 95, wherein the preferred shape of the fission propagation flame side is rotationally asymmetric around the second dimension.

97. A system for determining the preferred shape of a fission propagating fire flame surface along a second dimension in a plurality of fission fuel sub-assemblies, according to a selected set of dimensional constraints, for a fission progressive flame surface propagating along the first and second dimensions, 1 electrical circuit;

And a second electrical circuit configured to determine the movement of the selected fission fuel sub-assembly among the plurality of fission sub-fuel assemblies along the first dimension from each first position toward each second position in a manner responsive to a desired shape.

98. The system of 97, wherein the second electrical circuit is also configured to determine an existing shape of the fission progressive flame surface.

99. The method of paragraph 97 wherein the second electrical circuit includes a method of establishing a desired shape of movement of selected fissile fuel subassemblies from a plurality of fissile fuel subassemblies along a first dimension from respective first positions to respective second positions ≪ / RTI >

100. The method of clause 97 wherein the second electrical circuit is configured to move the selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from respective first positions to respective second positions in a manner that maintains a desired shape ≪ / RTI >

101. The method of clause 97 wherein the second electrical circuit is configured to move the selected fissile fuel sub-assembly of the plurality of fission sub-assemblies from their respective first positions toward their respective second positions in a desired configuration Wherein the system is also configured to determine in a responsive manner.

102. The system of paragraph 97 wherein the plurality of fission fuel sub-assemblies extend along a second dimension.

103. The system of 97, wherein the first dimension is substantially orthogonal to the long axis of the plurality of fission fuel sub-assemblies.

104. The system of paragraph 97, wherein the first dimension and the second dimension are substantially orthogonal to each other.

105. The system of 97, wherein the first dimension comprises a radial dimension and the second dimension comprises an axial dimension.

106. The system of 97, wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension.

107. The system of 97, wherein the first dimension comprises an axial dimension and the second dimension comprises a lateral dimension.

108. The system of 97, wherein the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

109. The system of 97, wherein the first position includes an outer position and the second position includes an inner position.

110. The system of clause 109, wherein the medial and lateral locations are determined by the geometric proximity to the center of the reactor core.

111. In a system as in clause 109, wherein the inner and outer positions are determined according to the neutron flux such that the neutron flux at the inner position is greater than the neutron flux at the outer position.

112. In the section 109, the inner position and the outer position are determined according to the reactivity of the _effective k from the inner position to be greater than the _effective k from the outer position system.

113. The system of paragraph 97, wherein the first position includes an inboard position and the second position includes an outboard position.

114. The system of clause 113, wherein the medial and lateral locations are determined by the geometric proximity to the center of the reactor core.

115. The system of clause 113, wherein the medial and lateral positions are determined according to the neutron flux such that the neutron flux at the medial position is larger than the neutron flux at the medial position.

116. In the section 113, the inner position and the outer position are determined according to the reactivity of the _effective k from the inner position to be greater than the _effective k from the outer position system.

117. The system of clause 97, wherein the first position and the second position are located on both sides of a reference value along the first dimension.

118. The system of 97, wherein the first location and the second location include at least one attribute that is substantially equivalent.

119. The system of clause 118, wherein the at least one property comprises a geometric proximity to a central portion of the reactor core.

120. The system of clause 118, wherein at least one property comprises a neutron flux.

121. The system of clause 118, wherein the at least one attribute comprises responsiveness.

122. The system of 97, wherein the second electrical circuit is also configured to determine rotation of at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

123. The system of 97, wherein the second electrical circuit is also configured to determine the flip of at least one selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies.

124. The system of clause 97, wherein the selected set of dimensional constraints comprises a predetermined maximum distance along a second dimension.

125. The system of clause 97, wherein the selected set of dimensional constraints is a function of at least one flame surface criterion.

126. In section 125, the flame surface standard includes the neutron flux.

127. The system of 126 wherein the neutron flux is associated with at least one selected fission fuel sub-assembly of a plurality of fission sub-assemblies.

128. In section 125, the flame surface standard includes a poetic atomic neutron flux.

129. The system of 128, wherein the poetic atom neutron is associated with at least one selected fission fuel sub-assembly of a plurality of fission sub-assemblies.

130. In Section 125, the flame surface standard includes the degree of combustion.

131. The system of claim 130, wherein the degree of combustion is associated with at least one selected fission fuel sub-assembly of the plurality of fission fuel sub-assemblies.

132. The system of clause 125, wherein the flame front reference comprises a flame surface position in at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

133. The method of clause 97, wherein the second electrical circuit is adapted to make a determination to move a selected fission fuel sub-assembly of a plurality of fission sub-assemblies from their respective first positions to their respective second positions in a radial direction along a first dimension Further comprising:

134. The method of clause 97, wherein the second electrical circuit is adapted to make a decision to move the selected fissile fuel sub-assembly of the plurality of fission sub-assemblies from their respective first positions to their respective second positions spirally along the first dimension .

135. The system of clause 97, wherein the second electrical circuit is also configured to make a decision to axially convert selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies.

136. The system of 97, wherein the first electrical circuit is also configured to determine a substantially spherical shape of the fission progressive flame side.

137. The system of 97, wherein the first electrical circuit is also configured to determine a continuous curve shape of the fission progressive flame side.

138. The system of paragraph 97, wherein the preferred shape of the fission progressive flame side is substantially rotationally symmetric about the second dimension.

138. The system of clause 97, wherein the preferred shape of the fission progressive flame side has a substantial n-fold rotational symmetry around the second dimension.

140. The system of paragraph 97 wherein the preferred shape of the fission propagation flame surface is asymmetric.

141. In section 140, the preferred shape of the fission propagation flame side is rotationally asymmetric around the second dimension.

142. A system for determining a preferred shape of a fission progressive flame surface along a second dimension in a plurality of fission subassemblies according to a selected set of dimensional constraints for a fission progressive flame surface propagating along first and second dimensions, 1 computer readable medium software program code;

A second computer readable medium software program configured to determine, in a manner responsive to a desired shape, movement of selected fission fuel sub-assemblies of a plurality of fission sub-fuel subassemblies along a first dimension from respective first positions toward respective second locations, A computer software program product, including code.

143. The computer program product of claim 142, wherein the second computer readable medium software program code is also configured to determine an existing shape of a fission progressive wave flame surface.

144. The method of claim 142, wherein the second computer readable medium software program code is programmed to cause the movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from a respective first location toward each second location, Wherein the computer program product is further configured to determine in a manner that establishes a shape.

[0158] [019] 145. The method of embodiment 142, wherein the second computer readable medium software program code is adapted to move the selected fissile fuel sub-assembly among a plurality of fission sub-fuel assemblies along a first dimension from each first location toward each second location, And is configured to determine in a manner that maintains a shape.

146. The method of claim 142, wherein the second computer readable medium software program code is to move a selected fission fuel sub-assembly of a plurality of fission sub-fuels from a respective first location toward a respective second location along a first dimension Wherein the computer program product is further configured to determine a time in a manner that is responsive to a desired shape.

147. The computer program product of clause 142, wherein the plurality of fissionable fuel subassemblies extends along a second dimension.

148. The computer program product of claim 142, wherein the first dimension is substantially orthogonal to the long axis of the plurality of fission fuel sub-assemblies.

149. The computer program product of clause 142, wherein the first dimension and the second dimension are substantially orthogonal to each other.

150. The computer software program product of claim 142, wherein the first dimension comprises a radial dimension and the second dimension comprises an axial dimension.

151. The computer software program product of claim 142, wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension.

152. The computer software program product of claim 142, wherein the first dimension comprises an axial dimension and the second dimension comprises a lateral dimension.

153. The computer program product of clause 142, wherein the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

[0112] 154. The computer program product of clause 142, wherein the first location includes an outer location and the second location includes an inner location.

155. In a computer software program product as defined in clause 154, wherein the medial position and the lateral position are determined by the geometric proximity to the center of the reactor core.

156. In a computer software program product as defined in clause 154, wherein the medial position and the medial position are determined according to the neutron flux such that the neutron flux at the medial position is greater than the neutron flux at the medial position.

157. In the section 154, the inner position and the outer position of the computer software program product is _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

[0218] 158. The computer program product of clause 142, wherein the first location includes an inward location and the second location includes an outward location.

159. In a computer software program product as defined in section 158, wherein the medial and lateral locations are determined by the geometric proximity to the center of the reactor core.

160. The computer software program product of claim 158 wherein the medial and lateral locations are determined by the neutron flux such that the neutron flux at the medial position is larger than the neutron flux at the medial position.

161. In the section 158, the inner position and the outer position of the computer software program product is _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

162. The computer program product of clause 142, wherein the first position and the second position are located on both sides of a reference value along the first dimension.

163. The computer software program product of clause 142, wherein the first location and the second location comprise at least one property that is substantially equivalent.

164. In a computer software program product as in clause 163, wherein at least one attribute includes geometric proximity to a central portion of the reactor core.

165. The computer program product of clause 163, wherein the at least one property comprises a neutron.

166. The computer program product of 163 wherein the at least one attribute comprises responsiveness.

167. The computer program product of clause 142, wherein the second electrical circuit is also configured to determine rotation of at least one selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies.

168. The computer program product of clause 142, wherein the second electrical circuit is also configured to determine the flipping of at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

169. The computer program product of clause 142, wherein the selected set of dimensional constraints comprises a predetermined maximum distance along a second dimension.

170. The computer software program product of claim 142, wherein the selected dimensional constraint set is a function of at least one flame surface criterion.

171. In section 170, a computer software program product in which the flame surface standard includes neutron flux.

172. A computer software program product, wherein the neutron flux is associated with at least one selected fission fuel sub-assembly of a plurality of fission sub-fuel assemblies.

173. In section 170, a computer software program product in which the flame surface standard includes a volumetric neutron flux.

174. In a computer software program product as in clause 173, the poetic atom neutron is associated with at least one selected fission fuel sub-assembly of a plurality of fission subsets.

175. In a computer software program product as defined in paragraph 170, wherein the flame surface standard includes a degree of flammability.

176. The computer program product of item 175, wherein the degree of combustion is associated with at least one selected fission fuel sub-assembly of the plurality of fission fuel sub-assemblies.

177. The computer software program product of clause 170, wherein the flame front reference comprises a flame surface position in at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

178. The method of clause 142, wherein the second computer readable medium software program code is adapted to code selected fissile fuel sub-assemblies of a plurality of fission sub-fuels from respective first positions to respective second locations in a radial direction along a first dimension And a third computer readable medium software program code configured to make a decision to move the computer software program product.

179. The method of claim 142, wherein the second computer readable medium software program code moves selected fissionable fuel sub-assemblies of a plurality of fission sub-fuels from each first location to each second location in a spiral manner along a first dimension And fourth computer readable medium software program code configured to make a decision to cause the computer to perform the steps of:

180. The method of claim 142, wherein the second computer readable medium software program code comprises fifth computer readable medium software program code configured to make a decision to axially transform a selected fissile fuel sub-assembly of a plurality of fission sub- A computer software program product.

181. The computer program product of Claim 142, wherein the first computer readable medium software program code comprises a seventh computer readable medium software program code configured to determine a substantially spherical shape of a fission progressive wave flame surface.

182. The computer program product of Claim 142, wherein the first computer readable medium software program code comprises an eighth computer readable medium software program code configured to determine a continuous curve shape of a fission progressive fire plane.

183. In a computer software program product, wherein the preferred shape of the fission progressive flame side is substantially rotationally symmetric about the second dimension.

184. In a computer software program product as in paragraph 142, wherein the preferred shape of the fission progressive flame side has a substantial n-fold rotational symmetry about the second dimension.

185. In Section 142, the preferred shape of the fission propagation flame side is an asymmetric computer software program product.

186. In Section 185, the preferred shape of the fission propagation flame side is rotationally asymmetric about the second dimension.

187. A system for determining the preferred shape of a fission progressive flame surface along a second dimension in a plurality of fission subassemblies according to a selected set of dimensional constraints for a fission progressive flame surface propagating along the first and second dimensions, 1 electrical circuit;

A second electrical circuit configured to determine, in a manner responsive to a desired shape, movement of the selected fissile fuel sub-assembly among the plurality of fission sub-fuel subassemblies along a first dimension from each first position to respective second positions;

And a sub-assembly configured to move the selected fissile fuel sub-assembly among the plurality of fissile fuel sub-assemblies in response to the second electrical circuit.

188. The system of 187, wherein the second electrical circuit is also configured to determine an existing shape of the fission progressive flame side.

189. The method of clause 187, wherein the second electrical circuit includes a method of establishing a desired shape of movement of a selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies along a first dimension from respective first positions to respective second positions ≪ / RTI >

190. The method of clause 187, wherein the second electrical circuit is configured to move the selected fissile fuel sub-assembly among the plurality of fission sub-fuels along the first dimension from each first position to each second position in a manner that maintains the desired shape ≪ / RTI >

191. The method of clause 187, wherein the second electrical circuit is configured to move the selected fissile fuel sub-assembly of the plurality of fission sub-assemblies from their respective first positions toward their respective second positions in a desired configuration Wherein the system is also configured to determine in a responsive manner.

192. The system of 187 wherein the plurality of fission fuel sub-assemblies extend along a second dimension.

193. The system of clause 187, wherein the first dimension is substantially orthogonal to the long axis of the plurality of fission fuel sub-assemblies.

194. The system of clause 187, wherein the first dimension and the second dimension are substantially orthogonal to each other.

195. The system of clause 187, wherein the first dimension comprises a radial dimension and the second dimension comprises an axial dimension.

196. The system of clause 187, wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension.

197. The system of clause 187, wherein the first dimension comprises an axial dimension and the second dimension comprises a lateral dimension.

198. The system of 187 wherein the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

199. The system of clause 187, wherein the first position includes an outer position and the second position includes an inner position.

200. The system of clause 199, wherein the medial and lateral locations are determined by the geometric proximity to the center of the reactor core.

201. The system of clause 199, wherein the medial position and the medial position are determined according to the neutron flux such that the neutron flux at the medial position is greater than the neutron flux at the medial position.

202. In the section 199, the inner position and an outer position in the _effective k from the inner position being determined according to the reactivity to be larger than the _effective k from the outer position system.

203. The system of clause 187, wherein the first position includes an inner position and the second position includes an outer position.

204. The system of clause 203, wherein the inner and outer locations are determined by the geometric proximity to the center of the reactor core.

205. The system of clause 203, wherein the medial position and the medial position are determined according to the neutron flux such that the neutron flux at the medial position is greater than the neutron flux at the medial position.

206. In the section 203, the inner position and the outer position are determined according to the reactivity of the _effective k from the inner position to be greater than the _effective k from the outer position system.

207. The system of clause 187, wherein the first position and the second position are located on both sides of a reference value along the first dimension.

208. The system of clause 187, wherein the first location and the second location comprise at least one attribute that is substantially equivalent.

209. The system of clause 208, wherein at least one property comprises geometric proximity to a central portion of the reactor core.

210. The system of clause 208, wherein at least one property comprises a neutron flux.

211. The system of clause 208, wherein at least one attribute comprises responsiveness.

212. The system of 187, wherein the second electrical circuit is also configured to determine rotation of at least one selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies.

213. The system of 187, wherein the second electrical circuit is also configured to determine the flip of at least one selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies.

214. The system of 187, wherein the subassembly comprises a nuclear fuel handling device.

215. The system of clause 187, wherein the subassembly is further configured to radially move selected fissile fuel sub-assemblies of the plurality of fissile fuel subassemblies from respective first positions to respective second positions.

216. The system of 187, wherein the subassembly is also configured to spiral a selected fissile fuel sub-assembly of a plurality of fissile fuel subassemblies from their respective first locations toward respective second locations.

217. The system of 187, wherein the subassembly is also configured to axially convert selected fissile fuel sub-assemblies of the plurality of fissile fuel subassemblies.

218. The system of 187, wherein the subassembly is also configured to rotate a selected fissile fuel sub-assembly of a plurality of fissile fuel subassemblies.

219. The system of 187, wherein the subassembly is also configured to invert a selected fission fuel sub-assembly of a plurality of fission sub-assemblies.

220. Nuclear Fission Reactor Reactor Core;

A plurality of fission fuel subassemblies accommodated in a nuclear fission traveling wave reactor core and configured to propagate a fission progressive flame surface therein along respective first and second dimensions;

A first electrical circuit configured to determine a desired shape of a fission progressive flame surface along a second dimension in a plurality of fission sub-assemblies according to a selected set of dimensional constraints;

A second electrical circuit configured to determine, in a manner responsive to a desired shape, movement of the selected fissile fuel sub-assembly among the plurality of fission sub-fuel subassemblies along a first dimension from each first position to respective second positions;

And a subassembly configured to move selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies in response to a second electrical circuit.

221. The nuclear fission progressive nuclear reactor of 220, wherein the second electrical circuit is also configured to determine an existing shape of the fission progressive flame surface.

222. The method of 220, wherein the second electrical circuit is a method of establishing a desired shape of movement of selected fissile fuel sub-assemblies from a plurality of fissile fuel sub-assemblies along a first dimension from respective first positions to respective second positions Of the nuclear reactor.

223. In 220, the second electrical circuit is configured to move the selected fissile fuel sub-assembly among a plurality of fissile fuel sub-assemblies that follow the first dimension from each first position to each second position in a manner that maintains the desired shape Of the nuclear reactor.

224. In 220, the second electrical circuit is configured to move the selected fissile fuel sub-assembly of the plurality of fission sub-assemblies from their respective first positions toward their respective second positions in a desired configuration And is also configured to determine in a responsive manner.

225. The nuclear fission propagation nuclear reactor of 220, wherein the plurality of fissile fuel subsets extend along a second dimension.

226. The nuclear fission progressive nuclear reactor of 220, wherein the first dimension is substantially orthogonal to the long axis of the plurality of fission sub-assemblies.

227. The nuclear fission traveling-wave reactor of clause 220, wherein the first dimension and the second dimension are substantially orthogonal to each other.

228. The nuclear fission traveling-wave reactor of clause 220, wherein the first dimension comprises a radial dimension and the second dimension comprises an axial dimension.

229. The nuclear-progressive reactor of clause 220, wherein the first dimension comprises an axial dimension and the second dimension comprises a radial dimension.

230. The nuclear fission traveling-wave reactor of 220, wherein the first dimension comprises an axial dimension and the second dimension comprises a lateral dimension.

231. The nuclear fission traveling-wave reactor of clause 220, wherein the first dimension comprises a lateral dimension and the second dimension comprises an axial dimension.

232. The nuclear fission traveling-wave reactor of clause 220, wherein the first location comprises an outer location and the second location comprises an inner location.

233. In section 232, the inside and outside locations are determined by the geometric proximity of the center of the reactor core to the nuclear fission propagation reactor.

234. In clause 232, the inner and outer positions are determined according to the neutron flux so that the neutron flux in the inner position is larger than the neutron flux in the outer position.

235. In clause 232, the inside and outside locations are determined responsively so that k _effective at the inside location is greater than k _effective at the outside location.

236. The nuclear fission traveling-wave reactor of clause 220, wherein the first location comprises an interior location and the second location comprises an exterior location.

237. In Section 236, the internal and external locations are determined by the geometric proximity of the center of the reactor core to the nuclear fission propagation reactor.

238. In a nuclear fission propagation reactor as set forth in Section 236, the inner and outer locations are such that the neutron flux at the inner location is greater than the neutron flux at the outer location.

239. In the section 236, the inner position and an outer position in a traveling wave nuclear fission reactor is _effective k at the inner position being determined according to the reactivity to be larger than the _effective k at the outer position.

240. The nuclear fission traveling-wave reactor of clause 220, wherein the first position and the second position are located on both sides of a reference value along the first dimension.

241. The nuclear forwarding nuclear reactor of clause 220, wherein the first location and the second location comprise at least one property that is substantially equivalent.

242. In section 241, at least one property includes geometric proximity to the center of the reactor core.

243. In section 241, at least one property is a nuclear fission propagation nuclear reactor containing a neutron flux.

244. In section 241, at least one attribute comprises reactivity.

245. The nuclear fission progressive nuclear reactor of 220, wherein the second electrical circuit is also configured to determine rotation of at least one selected fission fuel sub-assembly of the plurality of fission sub-assemblies.

246. The nuclear fission progressive nuclear reactor of 220, wherein the second electrical circuit is also configured to determine the flip of at least one selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies.

247. The nuclear fission propagation reactor of clause 220, wherein the selected set of dimensional constraints comprises a predetermined maximum distance along a second dimension.

248. In section 220, the selected dimensional confinement set is a function of at least one flame surface criterion.

249. In section 248, the fission surface standard includes a neutron flux.

250. The nuclear fission propagation nuclear reactor of 249, wherein the neutron flux is associated with at least one selected fission fuel sub-assembly of a plurality of fission sub-assemblies.

251. In section 248, the fission surface criterion is a fission progressive nuclear reactor containing a poetic atomic neutron.

252. In section 251, a nuclear fission nuclear reactor is one in which the poWer neutrons are associated with at least one selected fission fuel sub-assembly of a plurality of fission fuel sub-assemblies.

253. In paragraph 248, a nuclear fission propagation reactor in which the flame surface standard includes the degree of combustion.

254. In a fission propagation nuclear reactor as set forth in Section 253, the degree of combustion is associated with at least one selected fissile fuel sub-assembly of a plurality of fissile fuel sub-assemblies.

255. In paragraph 248, the fission surface criterion comprises a flame surface position in a selected fissile fuel sub-body of at least one of a plurality of fissile fuel sub-assemblies.

256. In 220, the second electrical circuit is adapted to make a determination to move selected fissile fuel sub-assemblies of the plurality of fission sub-fuels from their respective first positions to their respective second positions in a radial direction along a first dimension Also constructed is a nuclear fission propagation reactor.

257. In 220, the second electrical circuit is adapted to make a decision to move selected fissile fuel sub-assemblies of the plurality of fission sub-assemblies from their respective first positions to their respective second positions spirally along a first dimension A nuclear fission traveling wave reactor configured.

258. The nuclear fission progressive nuclear reactor of 220, wherein the second electrical circuit is also configured to make a decision to axially convert a selected fissile fuel sub-assembly of the plurality of fissile fuel sub-assemblies.

259. The nuclear fission progressive nuclear reactor of 220, wherein the first electrical circuit is also configured to determine a substantially spherical shape of the fission progressive flame surface.

260. The nuclear fission progressive nuclear reactor of 220, wherein the first electrical circuit is also configured to determine a continuous curved shape of the fission progressive flame side.

261. In Section 220, the preferred shape of the fission progressive flame surface is substantially rotationally symmetric about the second dimension.

262. The nuclear fission traveling-wave reactor of clause 220, wherein the preferred shape of the fission progressive flame surface has a substantial n-fold rotational symmetry about the second dimension.

263. In Section 220, the preferred shape of the fission propagation flame surface is an asymmetric progressive nuclear reactor.

264. In Section 263, the preferred shape of the fission progressive wave flame surface is a rotationally asymmetric fission progressive nuclear reactor around the second dimension.

265. In 220, the subassembly comprises a nuclear fuel handling device.

266. The nuclear forwarding nuclear reactor of clause 220, wherein the subassembly is also configured to radially move selected fissile fuel sub-assemblies of the plurality of fissile fuel subassemblies from respective first positions to respective second positions.

267. The nuclear forwarding nuclear reactor of clause 220, wherein the subassembly is also configured to spiral a selected fissile fuel sub-assembly of a plurality of fissile fuel subassemblies from a respective first position to respective second locations.

268. The nuclear forwarding nuclear reactor of clause 220, wherein the subassembly is also configured to axially convert a selected fissile fuel subassembly of a plurality of fissile fuel subassemblies.

269. The nuclear fission traveling-wave reactor of clause 220, wherein the subassembly is also configured to rotate a selected fissile fuel subassembly of a plurality of fissile fuel subassemblies.

270. The nuclear fission progressive nuclear reactor of 220, wherein the subassembly is also configured to invert a selected fissile fuel sub-assembly of a plurality of fissile fuel subassemblies.

271. In a method for operating a fission traveling wave reactor,

Moving at least one fission fuel assembly from a first location in the nuclear fission traveling wave reactor core to a second location in the nuclear fission traveling wave reactor core.

272. The method of 271, further comprising moving at least one fission fuel assembly from a second location inwardly.

273. The method of clause 271, wherein the first and second locations are determined by the geometric proximity to the center of the reactor core.

274. The method of clause 271, wherein the first position and the second position are determined according to the neutron flux such that the neutron flux at the first position is larger than the neutron flux at the second position.

275. In the section 271, in which the first position and the second position is to the _effective k from the first position determined according to the reactivity to be larger than the _effective k at the second position.

276. In a method for operating a fission traveling wave reactor,

Making a determination to move at least one fissile fuel assembly from a first location in a nuclear fission traveling wave reactor core to a second location in a fission traveling wave reactor core, different from the first location, in a first direction;

Making a determination to move at least one fission fuel assembly from a second position in a second direction different from the first direction.

277. The method of 276, wherein the first direction is an outward direction and the second direction is an inward direction.

278. The method of 277, wherein the first and second locations are determined by the geometric proximity to the center of the reactor core.

279. The method of clause 277, wherein the first position and the second position are determined according to the neutron flux such that the neutron flux at the first position is larger than the neutron flux at the second position.

280. In the section 277, in which the first position and the second position is to the _effective k from the first position determined according to the reactivity to be larger than the _effective k at the second position.

281. The method of 276, wherein the first direction is an inward direction and the second direction is an outward direction.

282. The method of 281, wherein the second location and the first location are determined by the geometric proximity to the center of the reactor core.

283. In Section 281, the second position and the first position are determined according to the neutron flux such that the neutron flux in the second position is larger than the neutron flux in the first position.

284. In the section 281, in which the second position and the first position is to the _effective k at a second location determined according to the reactivity to be larger than the _effective k from the first position.

285. In a method for operating a fission traveling wave reactor,

Moving at least one fissile fuel assembly from a first location in the nuclear fission traveling wave reactor core to a second location in the fission traveling wave reactor core, different from the first location, in a first direction;

Making a determination to move at least one fission fuel assembly from a second position in a second direction different from the first direction.

286. The method of 285 wherein the first direction is an outward direction and the second direction is an inward direction.

287. The method of 286 wherein the first position and the second position are determined by the geometric proximity to the center of the reactor core.

288. The method of clause 286, wherein the first position and the second position are determined according to the neutron flux so that the neutron flux at the first position is larger than the neutron flux at the second position.

289. In the section 286, in which the first position and the second position is to the _effective k from the first position determined according to the reactivity to be larger than the _effective k at the second position.

290. The method according to clause 285, wherein the first direction is an inward direction and the second direction is an outward direction.

291. The method of 290 wherein the second location and the first location are determined by the geometric proximity to the center of the reactor core.

292. The method of clause 290, wherein the second position and the first position are determined according to the neutron flux so that the neutron flux in the second position is larger than the neutron flux in the first position.

293. In the section 290, in which the second position and the first position is to the _effective k at a second location determined according to the reactivity to be larger than the _effective k from the first position.

294. A method of operating a fission traveling wave reactor,

Moving at least one fissile fuel assembly from a first location in the nuclear fission traveling wave reactor core to a second location in the fission traveling wave reactor core, different from the first location, in a first direction;

And moving at least one fission fuel assembly from a second position in a second direction different from the first direction.

295. The method of 294, wherein the first direction is an outward direction and the second direction is an inward direction.

296. The method of 295 wherein the first and second locations are determined by the geometric proximity to the center of the reactor core.

297. The method of clause 295, wherein the first position and the second position are determined according to the neutron flux so that the neutron flux at the first position is larger than the neutron flux at the second position.

298. In the section 295, in which the first position and the second position is to the _effective k from the first position determined according to the reactivity to be larger than the _effective k at the second position.

299. The method of 294, wherein the first direction is an inward direction and the second direction is an outward direction.

300. The method of clause 299, wherein the second location and the first location are determined by the geometric proximity to the center of the reactor core.

301. The method of clause 299, wherein the second position and the first position are determined according to the neutron flux such that the neutron flux at the second position is larger than the neutron flux at the first position.

302. In the section 299, in which the second position and the first position is to the _effective k at a second location determined according to the reactivity to be larger than the _effective k from the first position.

303. In a method for operating a fission reactor,

Selecting a predetermined combustion level;

Comprising the step of determining the movement of a selected fissile fuel assembly of a plurality of fissile fuel assemblies in a fission reactor core in such a manner as to achieve an equivalent burnup level towards a predetermined burnup level in substantially all of the plurality of fissile fuel assemblies .

304. The method of 303, further comprising moving a selected fissile fuel assembly of a plurality of fissile fuel assemblies in a fission nuclear reactor core in a manner responsive to a moving crystal.

305. A method as in claim 304, further comprising determining the removal of each selected fission fuels aggregate of the plurality of fission fuel assemblies when the flammability level is equalized toward a predetermined level of combustion level.

306. The method of 305, further comprising removing selected fissionable fuel assemblies from a plurality of fissionable fuel assemblies in response to removal determinations.

While various aspects and embodiments have been described so far, other aspects and embodiments will be apparent to those skilled in the art. The various aspects and embodiments described herein are for illustrative purposes only and are not intended to be limiting, and the true scope and spirit of the invention is indicated by the following claims.

Claims (106)

A method for controlling a nuclear fission traveling wave reactor,
A plurality of fission fuel subassemblies having an initial shape defined by a first dimension and a second dimension, the first dimension comprising a radial dimension and a plurality of fissile fuel subassemblies of the fission traveling wave nuclear reactor, The desired shape of the fission propagating wave flame surface along the second dimension within the plurality of fission fuel subassemblies is determined for a fission traveling wave flame front propagating along the second dimension including the axial dimension Determining according to a selected set of dimension constraints;
Determining migration of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions to respective second positions in a manner responsive to the desired shape Step
Lt; / RTI >
Wherein the fission progressive wave flame side is shortened along the axial dimension in the vicinity of the first positions to change the shape of the fission progressive flame surface and lengthens along the axial dimension in the vicinity of the second positions. Control method of nuclear fission traveling wave reactor. The method of claim 1, further comprising determining an existing shape of the fission progressive wave flame surface. 2. The method of claim 1, further comprising, responsive to the desired shape, movement of selected fission fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions Determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions to establish the desired shape Wherein the method comprises the steps of: 2. The method of claim 1, further comprising, responsive to the desired shape, movement of selected fission fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions Determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions to maintain the desired shape Wherein the method comprises the steps of: 2. The method of claim 1, further comprising the step of moving the selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies from their respective first positions toward their respective second positions along the first dimension, In response to a signal from the nuclear reactor. 2. The method of claim 1, further comprising: selecting a plurality of fissionable fuel sub-assemblies of the plurality of fission sub-fuels from the respective first positions toward respective second positions in a manner responsive to the desired shape, Wherein the method further comprises the step of: The method of claim 1, wherein the first dimension is orthogonal to an elongated axis of the plurality of fissile fuel subassemblies. 2. The method of claim 1, wherein the first dimension and the second dimension are orthogonal to each other. 2. The method of claim 1, wherein the first positions include outward positions and the second positions include inward positions. 10. The method of claim 9, wherein the inner and outer locations are selected such that the geometric proximity to the center of the reactor core, the neutron flux at the inner locations is greater than the neutron flux at the outer locations And reactivity such that k _effective at said inner positions is greater than k _effective at said outer positions. ≪ Desc / Clms Page number 20 > 2. The method of claim 1, wherein the first positions include inner positions and the second positions include outer positions. 12. The method of claim 11, wherein the inner and outer locations are configured such that the geometric proximity to the center of the reactor core, the neutron flux at the inner locations is greater than the neutron flux at the outer locations And reactivity such that k _effective at said inner positions is greater than k _effective at said outer positions. ≪ Desc / Clms Page number 20 > 2. The method of claim 1, wherein the first positions and the second positions are located on both sides of a reference value along the first dimension. 2. The method of claim 1, wherein the first positions and the second positions include at least one attribute that is the same. 15. The method of claim 14, wherein the at least one attribute comprises attributes selected from geometric proximity, neutron flux, and reactivity to a central region of the reactor core. The method of claim 1, wherein determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions comprises: And determining rotation of at least one of the selected fissile fuel subassemblies among the fissile fuel subassemblies of the fission subassembly. The method of claim 1, wherein determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions comprises: Determining the inversion of at least one of the selected fissile fuel subassemblies among the selected fissile fuel subassemblies of the fission subassembly. 2. The method of claim 1, wherein the selected set of dimension constraints comprises a predetermined maximum distance along the second dimension. 2. The method of claim 1, wherein the selected set of dimension constraints is a function of at least one flame surface criterion. 20. The method of claim 19, wherein the flame surface reference comprises a neutron flux. 21. The method of claim 20, wherein the neutron flux is associated with at least one of the selected fissile fuel subassemblies among the plurality of fissile fuel subassemblies. 20. The method of claim 19, wherein the flame surface reference comprises a poetic atomic neutron fluence. 24. The method of claim 22, wherein the poetic neutron flux is associated with at least one of the selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies. 20. The method of claim 19, wherein the flame surface reference comprises a burnup. 25. The method of claim 24, wherein the degree of combustion is associated with at least one of the selected fissile fuel subassemblies among the plurality of fissile fuel subassemblies. 20. The method of claim 19, wherein the flame surface reference comprises a flame surface position in at least one of the selected fissile fuel subassemblies among the plurality of fissile fuel subassemblies. The method of claim 1, wherein determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions comprises: Of the selected fissile fuel subassemblies of the plurality of fission subassemblies of each of the plurality of fission subassemblies of the plurality of fission subassemblies from each of the first positions toward respective second positions. The method of claim 1, wherein determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions comprises: And moving the selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies of each of the plurality of fission sub-assemblies of the plurality of fission sub-assemblies of the plurality of fission sub-assemblies of the plurality of fission sub-assemblies. The method of claim 1, wherein determining the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions comprises: And a crystal that translates the selected fissile fuel subassemblies among the fissile fuel subassemblies in the axial direction. The method of claim 1, wherein the desired shape of the fission progressive wave flame surface is selected from the group consisting of a sphere, a shape along a selected continuous curved surface, a rotationally symmetric shape about the second dimension, And a shape selected from a shape having a double rotational symmetry. The method of claim 1, wherein the desired shape of the fission progressive wave flame surface is asymmetrical. 32. The method of claim 31, wherein the desired shape of the fission progressive wave flame surface is rotationally asymmetric about the second dimension. A plurality of fission fuel subassemblies of said first dimension and nuclear fission propagation wave reactor having a radial dimension and an initial shape defined by a first dimension and a second dimension, Wherein the fissile propagation wave flame surface along the second dimension in the plurality of fissile fuel subassemblies with respect to a fission progressive wave flame front propagating along the second dimension including an axial dimension along a central axis, A first electrical circuit configured to determine a shape according to a selected set of dimension constraints;
To determine the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions in a manner responsive to the desired shape 2 Electrical circuit
Lt; / RTI >
Wherein the fission progressive wave flame side is shortened along the axial dimension in the vicinity of the first positions to change the shape of the fission progressive flame surface and lengthens along the axial dimension in the vicinity of the second positions. system. 34. The system of claim 33, wherein the second electrical circuit is further configured to determine an existing shape of the fission traveling wave flame surface. 34. The apparatus of claim 33, wherein the second electrical circuit is further configured to move selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions to respective second positions In a manner that establishes the desired shape. 34. The apparatus of claim 33, wherein the second electrical circuit is further configured to move selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions to respective second positions In a manner that maintains the desired shape. 34. The apparatus of claim 33, wherein the second electrical circuit is further configured to move selected fissile fuel sub-assemblies of the plurality of fission sub-fuel assemblies from their respective first positions toward respective second locations along the first dimension Wherein the system is configured to determine when to respond to the desired shape. 34. The system of claim 33, wherein the first dimension is orthogonal to a long axis of the plurality of fission fuel sub-assemblies. 34. The system of claim 33, wherein the first dimension and the second dimension are orthogonal to each other. 34. The system of claim 33, wherein the first locations include outer locations and the second locations include inner locations. 41. The method of claim 40, wherein the inner and outer locations are selected from the group consisting of: geometric proximity to a central portion of the reactor core, a neutron flux such that the neutron flux at the inner locations is greater than the neutron flux at the outer locations, _Wherein the k response at the inner positions is greater than the k _effective at the outer positions. 34. The system of claim 33, wherein the first locations include inner locations, and the second locations include outer locations. 43. The method of claim 42, wherein the inner and outer locations are selected from the group consisting of: geometric proximity to a central portion of a reactor core, a neutron flux such that the neutron flux at the inner locations is greater than the neutron flux at the outer locations, _Wherein the k response at the inner positions is greater than the k _effective at the outer positions. 34. The system of claim 33, wherein the first positions and the second positions are located on opposite sides of a reference value that follows the first dimension. 34. The system of claim 33, wherein the first locations and the second locations comprise at least one attribute that is the same. 46. The system of claim 45, wherein the at least one attribute comprises an attribute selected from geometric proximity to a central region of the reactor core, neutron flux, and reactivity. 34. The system of claim 33, wherein the second electrical circuit is further configured to determine rotation of at least one of the selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies. 34. The system of claim 33, wherein the second electrical circuit is further configured to determine flipping of at least one of the selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies. 34. The system of claim 33, wherein the selected set of dimension constraints comprises a predetermined maximum distance along the second dimension. 37. The system of claim 33, wherein the selected set of dimension constraints is a function of at least one flame surface criterion. 51. The system of claim 50, wherein the flame surface reference comprises a neutron flux. 52. The system of claim 51, wherein the neutron flux is associated with at least one fissile fuel sub-assembly of selected ones of the plurality of fissile fuel sub-assemblies. 51. The system of claim 50, wherein the flame surface reference comprises a poetic atom. 54. The system of claim 53, wherein the poetic neutron flux is associated with at least one fissile fuel sub-assembly of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies. 51. The system of claim 50, wherein the flame surface reference comprises a degree of combustion. 56. The system of claim 55, wherein the degree of combustion is associated with at least one fission fuel sub-assembly of the plurality of selected fissile fuel sub-assemblies. 51. The system of claim 50 wherein the flame surface reference comprises a flame surface position in at least one of the selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies. 34. The apparatus of claim 33, wherein the second electrical circuit is further configured to apply selected fissile fuel sub-assemblies of the plurality of fission sub-fuel assemblies from respective first positions to respective second positions along a radial To a < / RTI > 34. The apparatus of claim 33, wherein the second electrical circuit further comprises a plurality of fissile fuel subassemblies selected from the plurality of fissile fuel subassemblies, each of the plurality of fissile fuel subassemblies extending from respective first positions to respective second positions along a first dimension To a < / RTI > 34. The system of claim 33, wherein the second electrical circuit is further configured to make a determination to axially translate selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies. 34. The method of claim 33, wherein the first electrical circuit is further configured to generate a first electrical circuit having a sphere shape, a shape along a selected continuous curved surface, a rotationally symmetric shape about the second dimension, Wherein the system is configured to determine the shape of the fission progressive flame surface selected from the shapes having antiparallel symmetry. 34. The system of claim 33, wherein the desired shape of the fission progressive flame surface is asymmetric. 63. The system of claim 62, wherein the desired shape of the fission progressive flame surface is rotationally asymmetric about the second dimension. A computer-readable storage medium having stored thereon a computer software program,
A plurality of fission fuel subassemblies of said first dimension and nuclear fission propagation wave reactor having a radial dimension and an initial shape defined by a first dimension and a second dimension, Wherein the fissile propagation wave flame surface along the second dimension in the plurality of fissile fuel subassemblies with respect to a fission progressive wave flame front propagating along the second dimension including an axial dimension along a central axis, First computer readable medium software program code configured to determine a shape to be used in accordance with a selected set of dimension constraints;
To determine the movement of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies along the first dimension from respective first positions toward respective second positions in a manner responsive to the desired shape 2 computer readable medium software program code
Lt; / RTI >
Wherein the fission progressive wave flame side is shortened along the axial dimension in the vicinity of the first positions to change the shape of the fission progressive flame surface and lengthens along the axial dimension in the vicinity of the second positions. Readable storage medium. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code is configured to determine an existing shape of the fission progressive wave flame surface. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code further comprises: a selected fission subset of the plurality of fission subassemblies following the first dimension from respective first positions toward respective second locations And to determine the movement of the fuel sub-assemblies in a manner that establishes the desired shape. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code further comprises: a selected fission subset of the plurality of fission subassemblies following the first dimension from respective first positions toward respective second locations And to determine the movement of the fuel sub-assemblies in a manner that maintains the desired shape. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code further comprises means for selecting a plurality of the plurality of fission fuel subassemblies from each of the first locations to respective second locations, 1 dimension in response to the desired shape. ≪ Desc / Clms Page number 22 > 65. The computer readable storage medium of claim 64, wherein the first dimension is orthogonal to a long axis of the plurality of fission fuel subassemblies. 65. The computer readable medium of claim 64, wherein the first dimension and the second dimension are orthogonal to each other. 65. The computer readable medium of claim 64, wherein the first locations include outer locations and the second locations include inner locations. 74. The method of claim 71, wherein the inner and outer locations are geometric proximity to a center of the reactor core, a neutron flux such that the neutron flux at the inner locations is greater than the neutron flux at the outer locations, And the k response at the inner positions is greater than k _effective at the outer positions. &_Lt; Desc / Clms Page number ₂₄ > 65. The computer readable medium of claim 64, wherein the first locations include inner locations and the second locations include outer locations. 73. The method of claim 73, wherein the inner and outer locations include geometric proximity to a center of the reactor core, a neutron flux such that the neutron flux at the inner locations is greater than the neutron flux at the outer locations, And the k response at the inner positions is greater than k _effective at the outer positions. &_Lt; Desc / Clms Page number ₂₄ > 65. The computer readable medium of claim 64, wherein the first positions and the second positions are located on opposite sides of a reference value that follows the first dimension. 65. The computer-readable storage medium of claim 64, wherein the first locations and the second locations include at least one attribute that is the same. 77. The computer readable storage medium of claim 76, wherein the at least one attribute comprises attributes selected from geometric proximity to the central region of the reactor core, neutron flux, and reactivity. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code is further configured to determine rotation of at least one of the selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies Computer readable storage medium. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code is further configured to determine the flipping of at least one of the selected fission fuel subassemblies of the plurality of fission subassemblies, Computer readable storage medium. 65. The computer-readable medium of claim 64, wherein the selected set of dimension constraints comprises a predetermined maximum distance along the second dimension. 65. The computer-readable medium of claim 64, wherein the set of selected dimension constraints is a function of at least one flame surface criterion. 83. The computer readable storage medium of claim 81, wherein the flame surface reference comprises a neutron flux. 83. The computer readable storage medium of claim 82, wherein the neutron flux is associated with at least one fissile fuel sub-assembly of selected ones of the plurality of fissile fuel sub-assemblies. 83. The computer readable storage medium of claim 81, wherein the flame surface reference comprises a poetic atom. 85. The computer readable storage medium of claim 84, wherein the poetic neutron flux is associated with at least one fissile fuel sub-assembly of selected fissile fuel sub-assemblies of the plurality of fissile fuel sub-assemblies. 83. The computer readable storage medium of claim 81, wherein the flame surface reference comprises a degree of combustion. 87. The computer readable storage medium of claim 86, wherein the degree of combustion is associated with at least one fissile fuel sub-assembly of selected ones of the plurality of fissile fuel sub-assemblies. 83. The computer readable storage medium of claim 81, wherein the flame surface reference comprises a flame surface position in at least one of the selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code is further programmed to cause selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies from the respective first locations to respective second locations, And third computer readable medium software program code configured to make a decision to move radially along a dimension. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code is further programmed to cause selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies from the respective first locations to respective second locations, And fourth computer readable medium software program code configured to make a decision to move along a dimension in a spiral manner. 65. The computer readable medium of claim 64, wherein the second computer readable medium software program code further comprises: fifth computer readable medium software configured to axially translate selected fissile fuel subassemblies of the plurality of fissile fuel subassemblies, Readable storage medium having program code therein. 66. The computer readable medium of claim 64, wherein the first computer readable medium of software program code is program code for a computer readable medium having computer executable instructions for performing the steps of: And a sixth computer-readable medium software program code configured to determine a shape selected from a shape having an n-fold rotational symmetry. 65. The computer readable storage medium of claim 64, wherein the desired shape of the fission progressive flame surface is asymmetric. 93. The computer readable storage medium of claim 93, wherein the desired shape of the fission progressive flame surface is rotationally asymmetric about the second dimension. delete delete delete delete delete delete delete delete delete delete delete delete

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