KR20120083434A - A heat exchanger, methods therefor and a nuclear fission reactor system - Google Patents

Abstract

A heat exchanger, a method for this heat exchanger and a nuclear fission furnace system are disclosed. The heat exchanger includes a heat exchanger body that forms an exhaust plenum chamber therein shaped for uniform flow of the high temperature primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance to form a plurality of flow passages between the heat transfer members. The flow passage opens into the discharge plenum chamber. The spacing of the heat transfer members by a predetermined distance evenly distributes the primary heat transfer fluid through the flow passage, across the surfaces of the heat transfer members and into the discharge plenum chamber. Each heat transfer member is formed through the flow channel for the flow of the low temperature secondary heat transfer fluid. As the primary heat transfer fluid flows through the chamber and as the secondary heat transfer fluid flows through the flow channel at the same time, the heat transfer is from the hot primary heat transfer fluid to the cold secondary heat transfer fluid.

Description

Heat Exchanger, Method and Nuclear Fission Furnace System for Heat Exchanger

Cross-Reference to Related Applications

The present invention relates to and claims such benefit of the earliest available valid application date (s) from the application (s) listed below (“related applications”) (eg, in addition to the pseudonymized patent application). The claim of the earliest available priority date for, or the alias for, the related application (s), the patent application, or any and all parental applications, the grandparent of the parent, the parental source of the parent, or the like. Claiming interest under USC §119 (e)). All claims of related applications, and any and all parent applications, parent applications of parent applications, parent applications of parent applications, and the like, are hereby incorporated by reference unless such claims are inconsistent with the present application. do.

Related Applications:

In view of the USPTO extra-statutory requirement, the present application is filed on September 25, 2009, in the name of inventor Jon D. McWhirter, entitled "Heat exchanger, method and method for nuclear heat exchanger," a US patent. Consisting of a partial continuing application of Application 12 / 586,741, the United States patent application is such an application which is currently co-pending, or in which a co-pending application may enjoy the benefit of the filing date.

In consideration of the USPTO special law requirements, the present application is part of US patent application Ser. No. 12 / 653,656, filed December 15, 2009 in the name of inventor Jon D. McWhirter, entitled "Heat exchanger, method for heat exchange and nuclear fission system." Consisting of an ongoing application, the US patent application is such a co-pending application, or a co-pending application may enjoy the benefit of the filing date.

In view of the requirements of the USPTO Special Law, the present application is directed to US patent application Ser. No. 12 / 653,656, entitled "Heat Exchanger, Method and Method for Nuclear Fission Furnace System," filed December 15, 2009 in the name of inventor Jon D. McWhirter. Consisting of a partial continuing application, the U.S. patent application is such a co-pending application, or a co-pending application may enjoy the benefit of the filing date.

The United States Patent and Trademark Office (USPTO) is notified for entering into force by the United States Patent and Trademark Office computer program that a patent applicant is required to list both a serial number and whether the application is a continuing or partly pending application. Was done. "Stephen G. Kunin, Benefit of Prior-Filed Application, USPTO Official Gazette March 18, 2003" at http://www.uspto.gov/web/offices/com/sol/og/2003/weekl1/patbene.htm Reference. The Applicant Entity (hereinafter referred to as "Applicant") has been specifically described above with respect to the Applicant (s) on which the claim of priority is based, as prescribed by statute. Applicants understand that such statutes are clear in that particular reference language and do not require any characterization or serial number, such as "continued" or "partial," for priority claims on US patent applications. . Notwithstanding the foregoing, Applicants have understood that the US Patent and Trademark Office computer program requires certain data entry requirements, and as a result, Applicant has described this application as a partial continuation of the aforementioned parent application, but such description is the present application. In addition to the matter of this application (s), it is clear that no type of reference or recognition is made as to whether it contains any new content.

The present application relates generally to an induced nuclear reaction comprising a system, a process and elements for executing the process, and more particularly, to a heat exchanger, a method for a heat exchanger and a nuclear fission system, for example a vessel; Reactor core, primary heat exchanger, or pump submerged in the liquid coolant in the vessel).

In the operation of fission reactors, neutrons with known energy are absorbed by nuclides with high atomic weights. The resulting compound nucleus is separated into fission products comprising two low atomic weight fission fragments and decay products. Nuclides known to make such fission by all-energy neutrons are uranium-233, uranium-235 and plutonium-239, which are fissile nuclides. For example, thermal neutrons with a kinetic energy of 0.0253 eV (electron volts) can be used for nuclear fission of the U-235 nucleus. The fertile nuclides, Thorium-232 and Uranium-238, will not cause induced fission, except when using fast neutrons with kinetic energy of at least 1 MeV (million electron volts). The total kinetic energy released from each fission is about 200 MeV. This kinetic energy is converted into heat.

In a reactor, the aforementioned fissile and / or nuclear fuel material is typically contained within a plurality of densely packed fuel assemblies, which form the reactor core. Fissile and / or nuclear fuel material is a mixture of oxides of plutonium and uranium in the form of fuel pellets contained in fuel rods spaced from each other by wires or spacers spirally wound around each fuel rod. Can be.

In addition, in a commercial nuclear power reactor, the heat of fission is converted into electricity. In this regard, the primary coolant of the reactor is pumped through the reactor fuel assembly forming the reactor core and heated by the nuclear fission process. In some reactor designs, the heated primary coolant is sent to a steam generator, where the heated primary coolant transfers its heat to a secondary coolant (ie, water) disposed within the steam generator. The primary coolant is then returned back to the reactor core. A portion of the water that receives the heat of the primary coolant is vaporized into steam, which is then passed to a turbine-generator set to produce electricity. The steam passed through the turbine-generator set flows to the condenser, which condenses the steam into water, and the water is returned back to the steam generator.

A nuclear fission reactor of the type that can safely produce electricity is a pool-type liquid sodium fast breeder. In this regard, uranium-238 may be used as a nuclear material. Uranium-238 absorbs neutrons and is converted to fissile plutonium-239 by beta decay. When plutonium-239 again absorbs neutrons, nuclear fission occurs to produce heat. In high speed propagation furnaces, moderating materials such as water would not be desirable as coolant. Instead, in such a full-type liquid sodium fast propagation reactor, sodium is selected as the coolant because sodium does not thermally neutralize neutrons. In addition, due to the heat transfer properties of sodium, the reactor core may be operated at higher power densities, thereby reducing the size of the reactor. In addition, sodium melts at about 100 ° C. (about 212 ° F.) and boils at about 900 ° C. (about 1650 ° F.). Thus, sodium can be used at high temperatures without boiling, thus allowing high temperature and high pressure steam to be produced. This in turn increases the power plant thermal efficiency.

However, sodium coolant circulating through the reactor core becomes radioactive due to neutron absorption. This radioactivity allows reactor designers to use an intermediate heat exchange loop between the primary sodium coolant loop (s) and the steam generating loop. This lowers the risk of radioactive contamination of the turbine generator. In addition, steam generator pipe leakage may occur. If a leak occurs in the piping that carries sodium through the steam generator, the hot radioactive sodium passing through the steam generator will react violently with the water and steam in the steam generator. This will radioactively contaminate water and steam in the steam generator, thereby increasing the risk of radioactive contamination of the surrounding biosphere. For all the reasons mentioned above, in order to prevent the sodium in the core from making direct contact with the steam generator or turbine generator, the reactor designer uses an intermediate heat exchanger between the reactor core and the steam generator.

Thus, in the above-described full-type liquid sodium fast breeder reactor, the intermediate heat exchanger delimits the radioactive primary sodium in the reactor pool and the non-radioactive secondary sodium in the steam generator. In other words, typically, an intermediate heat exchanger disposed in the pool of liquid sodium with the reactor core removes heat from the high speed propagation furnace core and transfers the heat to an external steam generator.

Attempts have been made to provide adequate heat removal from fast nuclear fission reactor cores by using intermediate heat exchangers. US Pat. No. 4,294,658, entitled “Atomic Reactor,” issued October 13, 1981, in the name of Peter Humphreys et al., Discloses an intermediate heat exchanger, Electromagnetic flow coupler disposed within the base area of the module for driving the primary coolant through an intermediate exchanger and a heat exchanger, such patents in related secondary coolant circuits, for example caused by failure of the secondary coolant pump. In the event of an interruption in coolant flow, it relates to a severe thermal shock caused in an intermediate heat exchanger.According to this patent, the object of the present invention is to provide a pool in the event of an emergency with a flow interruption in the secondary coolant circuit. To reduce thermal shock caused by intermediate heat exchangers in liquid Will.

Another attempt to provide adequate heat removal from a fast nuclear fission reactor core by using an intermediate heat exchanger was issued on April 13, 1982, in the name of Michael G. Sowers, et al. Intermediate Heat Exchanger and Method Therefor, "US Patent No. 4,324,617. This patent discloses heat exchangers used in multi-pool, liquid metal cooled, reactors. This patent describes accommodating different thermal expansions between the structural parts of a heat exchanger. According to this patent, the shell of the heat exchanger is heated to a significantly higher temperature than the tubes in the heat exchanger by thermal communication with the hot pool and the tubes are tensioned during operation by the heating of the shell and thus the heat exchanger To accommodate different thermal expansions in the interior.

Although the techniques described herein disclose apparatus and methods for properly achieving their intended purpose, none of the techniques described herein are a heat exchanger as described in the specification and claims herein, a method for such a heat exchanger. And nuclear fission does not provide a system.

According to one aspect of the present invention, for use in connection with a pool-type nuclear fission furnace capable of generating heat, the pool wall may be disposed within pool fluid present in the pool-type nuclear fission furnace and trap the pool fluid. A heat exchanger that can be disposed proximate to an inner circumference and includes a heat exchanger body; And means integrally formed with the heat exchanger body for heat removal.

According to one further aspect of the present invention, there is provided a heat exchanger that can be disposed in a pool fluid present in a full-type nuclear fission reactor for use in connection with a full-type nuclear fission reactor capable of generating heat. The groups may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, the heat exchanger comprising a heat exchanger body having a surface defined for a portion of the plenum volume.

According to one further aspect of the present invention, there is provided a heat exchanger that can be disposed in a pool fluid present in a full-type nuclear fission reactor for use in connection with a full-type nuclear fission reactor capable of generating heat. The group may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, the heat exchanger comprising: a heat exchanger body defining a plenum volume shaped to a predetermined flow for the heat transfer fluid into the plenum volume, The heat exchanger body having a surface defining a portion of the plenum volume; And a heat transfer member coupled to the heat exchanger body and through the flow channel.

According to one further aspect of the present invention, there is provided a heat exchanger that can be disposed in a pool fluid present in a full-type nuclear fission reactor for use in connection with a full-type nuclear fission reactor capable of generating heat. The groups may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, wherein the heat exchanger is formed with a surface defining a portion of the plenum volume that is shaped for a predetermined flow of heat transfer fluid into the plenum volume. Heat exchanger body; And a plurality of adjacent heat transfer members in the heat exchanger body, the adjacent continuous heat transfer members being spaced apart by a predetermined distance to form a plurality of flow passages between opposing heat transfer members among the plurality of adjacent heat transfer members. And a plurality of adjacent heat transfer members adapted to distribute the flow of heat transfer fluid therethrough.

According to one aspect of the present invention, a system for use in connection with a full-type nuclear fission reactor is provided, such system comprising: a nuclear fission furnace core capable of generating heat; A heat exchanger body associated with the nuclear fission furnace core, the heat exchanger body comprising: a heat exchanger body that can be disposed in the pool fluid and proximate the inner circumference of the pool wall that traps the pool fluid; And means associated with the heat exchanger body for heat removal and in heat transfer communication with a core to the nuclear fission.

According to one aspect of the present invention, there is provided a system for use in connection with a full-type nuclear fission furnace, the system comprising: a vessel forming a pool wall having an inner perimeter, the pool wall having pool fluid therein. A vessel, configured to be confined; A nuclear fission furnace core that may be disposed within the vessel and generate heat; A heat exchanger body capable of heat transfer communication with a core through the nuclear fission, wherein the heat exchanger body may be disposed in the pool fluid close to the inner circumference of the pool wall, and the heat exchanger body may include a heat transfer fluid into the plenum volume. A heat exchanger body having a surface formed to define a portion of the plenum volume formed to achieve a predetermined flow of; And means associated with the heat exchanger body for heat removal and in heat transfer communication with a core to the nuclear fission.

According to one additional aspect of the present invention, there is provided a system for use in connection with a full-type nuclear fission reactor, the system comprising: a pressure vessel forming a pool wall having an inner perimeter, the pool wall being internally A pressure vessel, configured to trap pool fluid; A nuclear fission furnace core that can be disposed within the pressure vessel and generate heat; A heat exchanger body capable of heat transfer communication with a core by means of nuclear fission, wherein the heat exchanger body may be disposed within the pool fluid proximate the inner circumference of the pool wall, wherein the heat exchanger body has a heat transfer fluid into the plenum volume. A heat exchanger body having a surface defined therein that defines a portion of the plenum volume formed to achieve a predetermined flow of the heat exchanger body; And a plurality of adjacent heat transfer members coupled to the heat exchanger body, the plurality of adjacent heat transfer members being spaced apart by a predetermined distance to form a plurality of flow passages between opposing heat transfer members among the plurality of adjacent heat transfer members. And a plurality of adjacent heat transfer members adapted to distribute the flow of the heat transfer fluid through the flow passages.

According to a further aspect of the present invention, there is provided a method of assembling a heat exchanger that can be disposed in a pool fluid present in a full-type nuclear fission reactor for use in connection with a full-type nuclear fission reactor capable of generating heat, and The heat exchanger may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, the method comprising: receiving a heat exchanger body, and coupling means for removing heat to the heat exchanger body. do.

According to a further aspect of the present invention, there is provided a method of assembling a heat exchanger that can be disposed in a pool fluid present in a pool-type nuclear reactor for use in connection with a full-type nuclear reactor, the heat exchanger confining the pool fluid. Can be disposed proximate to the inner circumference of the pool wall, the method comprising receiving a heat exchanger body having a surface defining a portion of the plenum volume.

According to one aspect of the present invention, there is provided a method of assembling a heat exchanger that can be disposed in a pool fluid present in a full-type nuclear fission furnace for use in connection with a full-type nuclear fission reactor capable of generating heat, The heat exchanger may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, the method comprising: a heat exchange to define a plenum volume therein shaped for a predetermined flow of heat transfer fluid into the plenum volume A main body accommodating step, the heat exchanger main body accommodating step having a surface defining a portion of the plenum volume; And coupling a heat transfer member to the heat exchanger body, wherein the heat transfer member penetrates through the flow channel.

According to one aspect of the present invention, there is provided a method of assembling a heat exchanger that can be disposed in a pool fluid present in a full-type nuclear fission furnace for use in connection with a full-type nuclear fission reactor capable of generating heat, The heat exchanger may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, the method comprising: a surface defining a portion of the plenum volume shaped to a predetermined flow of heat transfer fluid into the plenum volume Receiving the formed heat exchanger body; And connecting a plurality of adjacent heat transfer members to the heat exchanger body, wherein the plurality of adjacent heat transfer members are opposed heat transfer members of the plurality of adjacent heat transfer members to distribute the flow of heat transfer fluid through the plurality of flow passages. Spaced apart by a predetermined distance to form a plurality of flow passages therebetween.

It is a feature of the present invention to provide a heat exchanger body that forms a chamber therein shaped for uniform flow of heat transfer fluid through the chamber.

Another feature of the invention is that a heat exchanger is spaced apart by a predetermined distance to form a plurality of flow passages between opposing heat transfer members of a plurality of adjacent heat transfer members for distributing flow of heat transfer fluid through the plurality of flow passages. A plurality of adjacent heat transfer members connected to a main body are provided.

In addition to the foregoing, aspects of various other methods and / or devices are developed and described in the teachings such as the description herein (eg, claims and / or details) and / or drawings.

The foregoing is a summary and may therefore include simplification, generalization, inclusion, and / or omission of specific matters; As a result, those skilled in the art will understand that such summaries are illustrative only and are not limiting in any way. In addition to the aspects, embodiments, and features for the foregoing description, additional aspects, embodiments, and features will be clearly understood upon reference to the following detailed description and drawings.

Although the specification ends with the claims particularly pointed out and specifically claimed by the present invention, the invention will be better understood from the following detailed description with reference to the accompanying drawings. In addition, the same reference numerals in different drawings will typically indicate the same or similar items.
1 is a schematic diagram illustrating a nuclear fission system.
2 is a horizontal cross-sectional view of a hexagonal-shaped nuclear fission furnace core comprising a plurality of nuclear fission module and a breather fuel module.
3 is a horizontal cross-sectional view illustrating one of the plurality of nuclear fission furnace modules and a plurality of control rods therein;
4 is a horizontal cross-sectional view of the nuclear fuel rod, with portions removed for clarity.
5 is a horizontal cross-sectional view of a parallelepiped-shaped nuclear fission furnace core including a plurality of nuclear fission furnace modules and a breather fuel module.
FIG. 6 is a vertical cross-sectional view of three exemplary nuclear fission furnace modules with some removed for clarity.
7 is an isometric view of a heat exchanger.
8 is an isometric view of the heat exchanger in cross section and in part of a dotted line.
8A is a view showing a guide structure, which is an isometric view showing the heat exchanger in cross section.
FIG. 9 is a vertical cross-sectional view of a heat exchanger showing cross-flow of the primary heat transfer fluid and the secondary heat transfer fluid. FIG.
FIG. 9A is a vertical cross-sectional view of a heat exchanger showing counter-flow of the primary heat transfer fluid and the secondary heat transfer fluid. FIG.
FIG. 9B shows a countercurrent flow of the primary heat transfer fluid and the secondary heat transfer fluid and is an exploded isometric view of the heat exchanger shown in FIG. 9A with portions removed for clarity.
FIG. 9C shows a co-current flow of a primary heat transfer fluid and a secondary heat transfer fluid, and is a vertical cross-sectional view of the heat exchanger. FIG.
FIG. 9D shows a co-current flow of a primary heat transfer fluid and a secondary heat transfer fluid, an exploded isometric view of the heat exchanger shown in FIG. 9C with portions removed for clarity.
10 is an isometric view of a heat transfer member having a plurality of fins on its outer surface.
11 is an isometric view of a heat transfer member with a plurality of nodules on its outer surface.
12 is an isometric view of a heat transfer member having a plurality of fins on its inner surface.
13 is an isometric view showing a heat transfer member forming a through flow channel and a plurality of conduits disposed along the flow channel.
FIG. 13A is an isometric view of a heat transfer member with wedge-shaped fins on its outer surface. FIG.
13B is an isometric view of a heat transfer member having a nodule with increased density on its outer surface.
14 is a schematic diagram illustrating a plurality of heat exchangers disposed in a pressure vessel.
15 is a cross-sectional view taken along section line 15-15 of FIG.
FIG. 16 illustrates a plurality of contiguous heat exchangers disposed in a pressure vessel, in which a horizontal cross section of the pressure vessel belonging to the nuclear fission system.
17-47 are flow diagrams illustrating a heat exchanger assembly method for use in connection with a nuclear fission furnace.

In the following detailed description, reference is made to the accompanying drawings, which form a part of this specification. In the drawings, like reference numerals generally refer to like components unless otherwise indicated. The illustrative embodiments described in the detailed description, drawings, and claims are not limiting. Even within the spirit or scope of the subject matter presented herein, other embodiments may be utilized and other changes may be made.

In addition, the present application uses formal outline headings for clarity. However, it will be appreciated that such outline headings are for illustrative purposes, and that other types of claimed subject matter may be described throughout this disclosure (eg, device (s) / structure (s) may be process (s)). / Job may be described under the heading (s) and / or process (s) / job may be described under the device (s) / structure (s) heading (s); and / or a single topic ) May span two or three or more headings). As such, the use of formal outline headings is in no way restrictive.

In addition, the subject matter described herein describes other components contained within, or linked to, other components. It will be appreciated that the architectures so described are merely exemplary, and many other configurations are possible in practice that may achieve the same functionality in practice. In a conceptual sense, the alignment of any components to achieve the same function can be effectively “associated” to achieve the desired function. As such, any two components combined to achieve a particular function herein may be viewed as “associated with” one another to achieve the desired function, regardless of the components or intermediate components. Similarly, any two components so associated may also be viewed as "operably linked" or "operably coupled" with each other to achieve the desired function, and any two components that may be so associated. The components may also be shown to be "operably coupled." Certain examples of operatively coupleable include, but are not limited to, physically matable and / or physically interacting components, and / or wirelessly interacting, and / or wirelessly Components that interact with, and / or that interact logically, and / or that may interact logically.

In some instances, one or more components herein may be “configured”, “configurable”, “operable / operable”, “adjusted / adjustable”, “can”, “matching ( conformable / consistent ", and the like. Those skilled in the art will appreciate that the phrase “consisting of” may generally include active-state components and / or inactive-state components and / or atmospheric-state components, unless other contexts are required.

Thus, referring to FIG. 1, a full-type fast neutron fission reactor and system, shown by way of example and not limitation, and generally designated by reference numeral 10, is shown. As described in more detail below, the nuclear fission system 10 may be a "traveling wave" nuclear fission system. The nuclear fission system 10 generates electricity, which is transmitted to an electrical user through a plurality of transmission lines (not shown). Instead, the nuclear fission system 10 may be used to perform a test, such as a test to determine the effect of temperature on the reactor material.

Referring to FIGS. 1, 2 and 3, the nuclear fission system 10 includes a nuclear fission reactor core, generally indicated at 20, wherein the core comprises a plurality of nuclear fission fuel assemblies or, as referred to herein, A nuclear fission module 30. The nuclear fission furnace core 20 is hermetically received in the reactor core sheath 40. By way of example only and not limitation, each fission module 30 may form a structure having a hexagon-shape in the transverse cross section, as shown, so that the other fission module 30 may be a reactor core. It may be densely packed together in (20), such packing will also be dense when compared to other shapes of fission modules, such as cylindrical or spherical shapes. Each nuclear fission module 30 includes a plurality of fuel rods 50 that generate heat due to the nuclear fission chain reaction process described above. If necessary, to add structural rigidity to the fission module 30 and to segregate the fission modules 30 from each other when the fission module 30 is disposed within the core 20 with fission. In order to do this, a plurality of fuel rods 50 may be surrounded by the fuel rod canister 60. Isolating the nuclear fission module 30 from each other prevents cross coolant cross flow between the fuel rods 50. Avoidance of lateral coolant crossflow flow prevents lateral vibration of the fuel rods 50. If such lateral vibrations occur, such lateral vibrations may increase the risk of damage to the fuel rod 50. Insulating the fission modules 30 from each other can also allow control of coolant flow on separate module-by-module bases. For example, controlling the coolant flow for the individual fission module 30 by directing the coolant flow in accordance with a non-uniform temperature distribution in the reactor core 20 may result in a coolant flow in the reactor core 20. Manage effectively In other words, more coolant will be directed to the nuclear fission modules 30 having a higher temperature in order to provide a substantially uniform temperature distribution across the reactor core 20. For an exemplary sodium cooled reactor in normal operation, the coolant has an average nominal volume flow rate of about 5.5 m ³ / sec (ie about 194 cubic ft ³ / sec) and about 2.3 m / sec. (Ie, about 7.55 ft / sec). The fuel rods 50 form fuel rod coolant flow channels 80 (see FIG. 6) therebetween to allow flow of coolant adjacent to each other and along the outside of the fuel rod 50. Canister 60 may include means (not shown) for supporting and tying fuel rods 50 together. Accordingly, the fuel rods 50 are bundled together in the canister 60 to form the hexagonal fission module 30 described above. Although the fuel rods 50 are adjacent to each other, as known to those skilled in the nuclear reactor design, the fuel rods 50 nevertheless remain in a spaced apart relationship by the outer ear wrapper 90 (see FIG. 6). The wire wrapper spirally surrounds and extends along the length of each fuel rod 50 in a serpentine manner.

Referring to Figure 3, a plurality of spaced apart, longitudinally extending and longitudinally movable control rods 95 (only a portion thereof) are disposed in the control rod guide tube or cladding (not shown), respectively. Control rods 95 are arranged symmetrically within the selected nuclear fission module 30 and extend the length of the predetermined number of nuclear fission modules 30. Control rods 95, shown as disposed within a predetermined number of hexagonal-shaped fission modules 30, control the neutron fission reactions occurring within the fission module 30. In other words, the control rod 95 comprises a suitable neutron absorber material having an acceptable high neutron absorbing cross section. In this regard, the absorber material is a metal or metalloid selected from the group consisting essentially of lithium, silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, erbium, europium, and mixtures thereof. Can be. Instead, the absorber material is a compound or alloy selected from the group consisting essentially of silver-indium-cadmium, boron carbide, zirconium diboride, titanium diboride, hafnium diboride, gadolinium titanate, dysprosium titanate, and mixtures thereof. Could be. Accordingly, the control rod 95 provides the reactor core 20 with reactivity management capability. In other words, the control rod 95 can control the neutron flux profile across the core 20 with nuclear fission and thus affect the temperature within the core 20 with the nuclear fission.

With particular reference to FIGS. 2, 3, and 4, each fuel rod 50 has a plurality of fuel pellets 100 stacked therein in an end-to-end manner, wherein the fuel pellets 100 are fuel rods 100. It is hermetically surrounded by the cladding material 110. The nuclear fuel pellet 100 comprises the fissile nuclide described above, for example, uranium-235, uranium-233 or plutonium-239. Instead, the fuel pellet 100 may comprise nuclear nuclear species, for example, thorium-232 and / or uranium-238, which may be denatured to the fissile nuclide described directly above, for example, via neutron capture during the fission process. It may include. Such nuclear fuel nuclide material may be contained within a breather rod disposed within a specially designated breather fuel module 115. As is known to those skilled in the art of high speed neutron propagation furnace design, such breather fuel modules 115 may be aligned as "breeding blankets" around the inner circumference of nuclear fission furnace core 20 for bridging nuclear fuel. There will be. As a further alternative, the nuclear fuel pellets 100 may comprise a predetermined mixture of fissile and nuclear material nuclides.

Referring to FIG. 4, by way of example only and not of limitation, the fuel pellet 100 may comprise uranium monooxide (UO), uranium dioxide (U0 ₂ ), thorium dioxide (Th0 ₂ ) (also referred to as thorium oxide), It may be made of an oxide (oxide) selected from the group consisting essentially of uranium trioxide (U0 ₃ ), uranium oxide-plutonium oxide (UO-PuO), triuranium octoxide (U ₃ 0 ₈ ) and mixtures thereof. . Instead, nuclear fuel pellets 100 may include substantially uranium alloyed or unalloyed with other metals, such as, but not limited to, zirconium or thorium metals, for example. As yet another alternative, nuclear fuel pellets 100 may comprise substantially carbide of uranium (UC _X ) or thorium carbide (ThC _x ). For example, nuclear fuel pellets 100 may comprise uranium monocarbide (UC), uranium dicarbide (UC ₂ ), uranium sesquicarbide (U ₂ C ₃ ), thorium dicarbide (ThC ₂ ), thorium carbide (ThC) And carbides selected from the group consisting essentially of these. As another non-limiting example, the nuclear fuel pellets 100 may comprise uranium nitride (U ₃ N ₂ ), uranium nitride-zirconium nitride (U ₃ N ₂ Zr ₃ N ₄ ), uranium-plutonium nitride It may be made of nitride (nitride) selected from the group consisting essentially of ((U-Pu) N), thorium nitride (ThN) and mixtures thereof. The fuel rod cladding material 110 sealingly surrounding the stack of nuclear fuel pellets 100 may be a suitable zirconium alloy such as ZIRCOLOY ™ (trade name of Westinghouse Electric Corporation) having known corrosion resistance and uniformity. The cladding material 110 may be made from other materials such as ferritic martensitic steel.

Referring back to FIG. 1, in order to prevent radioactive material, gas or liquid from leaking from the reactor core 20 into the surrounding biosphere, the nuclear fission core 20 may be a vault or reactor pressure vessel. 120). For the reasons described below, the pressure vessel 120 with the inner wall surface 122 is substantially with a pool of fluid or coolant 125 such as liquid sodium to the extent that the core 20 is submerged in the pool of coolant by nuclear fission. It is filled. The pressure vessel 120 may be made of steel, concrete, or other material of suitable size and thickness that may reduce the risk of radiation leakage and support the required pressure load. In addition, containment sealingly surrounding portions of the system 10 in order to further prevent radioactive particles, gases or liquids from leaking from the reactor core 20 into the surrounding biosphere. ) Vessels (not shown) may be present.

Referring again to FIG. 1, the primary loop coolant pipe 130 is allowed to flow through the reactor core 20 along an arrow 135 indicating the direction to allow cooling of the core 20 with nuclear fission. Is coupled to the core 20 by nuclear fission. The primary loop coolant pipe 130 may be made of any suitable material, for example stainless steel. If desired, the primary loop coolant pipe 130 may be made of ferrous alloys as well as non-ferrous alloys, zirconium based alloys, or other suitable structural materials or composites. The coolant delivered by the primary loop coolant pipe 130 may be a liquid metal selected from the group consisting essentially of sodium, potassium, lithium, lead and mixtures thereof. On the other hand, the coolant may be a metal alloy such as lead-bismuth (Pb-Bi). Instead, in an exemplary embodiment contemplated herein, the coolant is a sodium metal mixture such as liquid sodium (Na) metal or sodium-potassium (Na-K). Depending on the particular reactor core design and operating history, the normal operating temperature of the sodium-cooled reactor core may be relatively high. For example, in the case of 500 to 1,500 MWe sodium-cooled reactors using mixed uranium-plutonium oxide fuel, the reactor core outlet temperature is from about 510 ° C. (ie 950 ° F.) to about 550 ° C. (ie, during normal operation). , 1020 ° F). On the one hand, during a Loss of Coolant Accident (LOCA) or Loss of Flow Transient Accident (LOFTA), the peak fuel cladding temperature may reach about 600 ° C. (ie, 1110 ° F.) or above. This may vary depending on the reactor core design and operating history. In addition, decay heat accumulation during post-LOCA or post-LOFTA-case scenarios and also during shutdown of the reactor operation may produce unacceptable heat accumulation. Thus, in some cases, it is desirable to remove heat generated by core 20 with nuclear fission during normal operation and during post-incident scenarios.

Still referring to FIG. 1, the heat-bearing coolant produced by the nuclear fission furnace core 20 flows along the coolant flow stream or flow path 140 to the intermediate heat exchanger 150, and the intermediate heat exchanger also Submerged in coolant pool 125. The intermediate heat exchanger 150 may be made of any suitable material having a heat and corrosion resistance effect on the sodium coolant in the coolant pool 125, for example, suitable stainless steel. As described in more detail below, coolant flow along the coolant flow path 140 flows through the intermediate heat exchanger 150 and continues to flow through the primary loop coolant pipe 130. As will be described in more detail below, it will be appreciated that due to heat exchange occurring within the intermediate heat exchanger 150, the coolant leaving the intermediate heat exchanger 150 is cooled. It may be an electro-mechanical pump to pump the reactor coolant through the primary loop coolant pipe 130, through the reactor core 20, along the coolant flow path 140 and into the intermediate heat exchanger 150. The first pump 170 is coupled to the primary loop coolant pipe 130 and is in fluid communication with the reactor coolant carried by the primary loop coolant pipe 130.

Referring again to FIG. 1, a secondary loop pipe 180 is provided to remove heat from the intermediate heat exchanger 150. Secondary loop pipe 180 includes a secondary “hot” leg pipe segment 190 and a secondary “cold” leg pipe segment 200. The secondary high temperature leg pipe segment 190 and the secondary low temperature leg pipe segment 200 are integrally connected to the intermediate heat exchanger 150. Secondary loop pipe 180 comprising hot leg pipe segment 190 and cold leg pipe segment 200 comprises a fluid such as a liquid metal selected from the group consisting essentially of sodium, potassium, lithium, lead and mixtures thereof. do. On the other hand, the fluid may be a metal alloy such as lead-bismuth (Pb-Bi). Instead, in the exemplary embodiment contemplated herein, the fluid may suitably be liquid sodium (Na) metal or sodium metal mixture, such as sodium-potassium (Na-K). The secondary high temperature leg pipe segment 190 extends from the intermediate heat exchanger 150 to the steam generator and superheater combination 210 (hereinafter referred to as “steam generator 210”) for the reasons immediately below. Explain. In this regard, after passing through the steam generator 210, the coolant flowing through the secondary loop pipe 180 and exiting the steam generator 210 is lower in temperature and enthalpy than before entering the steam generator 210. This is due to heat exchange made in the steam generator 210. After passing through the steam generator 210, by means of a second pump 220, which may be an electro-mechanical pump, for example, a "low temperature" extending into the intermediate heat exchanger 150 to provide the aforementioned heat transfer. Coolant is pumped along the leg pipe segment 200. The manner in which the steam generator 210 produces steam is outlined directly below.

Referring again to FIG. 1, a body 230 of water having a predetermined temperature and pressure is disposed within the steam generator 210. The fluid flowing through the secondary hot leg pipe segment 190 will transfer its heat to the body of water 230 by conduction, and the body of water will have a lower temperature than the fluid flowing through the secondary hot leg pipe segment 190. Have As the fluid flowing through the secondary hot leg pipe segment 190 transfers its heat to the body of water 230, a portion of the body of water 230 vapors, depending on the predetermined temperature and pressure in the steam generator 210. Will evaporate to 240. The steam 240 will then proceed through the steam line 250, which has one end in vapor phase communication with the steam 240 and the other end in liquid communication with the body 230 of water. A rotatable turbine 260 is coupled to the steam line 250, so that the turbine 260 rotates as the steam 240 passes. For example, generator 270 coupled to turbine 260 by rotatable turbine shaft 280 produces electricity as turbine 260 is rotated. In addition, a condenser 290 is coupled to the steam line 250 and receives the steam passed through the turbine 260. Condenser 290 condenses the vapor into liquid water and delivers any waste heat to a heat sink such as cooling tower 300 associated with condenser 290. Liquid water condensed by the condenser 290 is pumped by the third pump 310 from the condenser 290 to the steam generator 210 along the steam line 250, and the third pump is connected to the condenser 290. It may be an electro-mechanical pump disposed between the steam generators 210.

As best shown in FIG. 5, the fission module 30 may be aligned to form a core configuration with parallelogram-shaped fission, generally designated as '222', instead of the hexagon-shaped configuration described above. There will be. In this regard, the reactor core sheath 40 of the nuclear fission core 222 includes a first end 330 and a second end 340, which will be described later.

Referring again to FIG. 5, regardless of the configuration selected for the nuclear fission core, the nuclear fission core 20 or 222 may be configured as a traveling wave nuclear fission core. In this regard, a relatively small and removable fission igniter 350 may include, but is not limited to, isotopic enrichment of fissile material such as U-233, U-235 or Pu-239. Is suitably positioned within the reactor core 222. By way of example only and not limitation, igniter 350 may be positioned adjacent to first end 330 opposite to second end 340 of reactor core 222. Neutrons are emitted by the igniter 350. Neutrons emitted by the igniter 350 are captured by the fissile and / or nuclear material in the fission module 30 to initiate the fission chain reaction. If necessary, if the fission chain reaction is self-sustaining, the igniter 350 may be removed.

Still referring to FIG. 5, igniter 350 initiates a three-dimensional defragration wave or “burn wave” 360. When the igniter 350 emits neutrons to cause "ignition", the combustion wave 360 is from the igniter 350 proximate to the first end 330 and from the second end 340 of the reactor core 222. Moving outwards, thereby forming a combustion wave 360 that propagates or propagates accordingly. In other words, as the combustion wave 360 propagates through the reactor core 222, each nuclear fission module 30 may receive at least a portion of the traveling combustion wave 360. The speed of the traveling combustion wave 360 may or may not be constant. Accordingly, the speed at which the combustion wave 360 propagates may be controlled. For example, the longitudinal motion of the aforementioned control rod 95 (see FIG. 3), in a predetermined or programmed manner, can lower or degrade the neutron reactivity of the fuel rod 50 disposed within the nuclear fission module 30. have. In this manner, the neutron reactivity of the fuel rod 50 that is combusted at the location of the combustion wave 360 is lowered or dropped relative to the neutron reactivity of the “unburned” fuel rod 50 in front of the combustion wave 360. do. This result provides the combustion wave propagation direction indicated by the arrow 365 indicating the direction. Controlling the responsiveness in this manner maximizes the propagation speed of the combustion wave 360 subject to operating constraints on the reactor core 220. For example, maximization of the propagation velocity of the combustion wave 360 is, in part, limited by the neutron influence of the reactor core structural material, and means for controlling the burn-up above the minimum value required for propagation. Provide a set of values.

The basic principle of such a traveling nuclear fission reactor is the co-pending US patent application entitled "Automated Nuclear Power Reactor For Long-Term Operation," filed November 28, 2006, in the name of Roderick A. Hyde et al. 605,943, more specifically, such US patent application is assigned to the assignee of the applicant, the entire disclosure of which is incorporated herein by reference.

Referring to FIG. 6, upright, adjacent hexagonal-shaped fission modules 30 are shown. Only three adjacent fission modules 30 are shown and it will be appreciated that a larger number of fission modules 30 are present in the reactor core 20. Each nuclear fission module 30 is mounted on a horizontal extension reactor core lower support plate 370. The reactor core lower support plate 370 extends properly across the bottom end portion of all nuclear fission modules 30. The reactor core lower support plate 370 has a corresponding bore 380 therethrough, which will be described below. The corresponding bore 380 has an open end 390 to allow coolant flow therein. The reactor core upper support plate 400 extends horizontally across the outlet or top end portions of all nuclear fission modules 30 and is removably connected to the nuclear fission module 30, wherein the upper support plates 400 are attached. Caps all nuclear fission modules 30. Reactor core upper support plate 400 also defines a plurality of flow slots 410 to allow cold through flow. The plurality of loop coolant pipes 130 and the first pump 170 (see FIG. 1) deliver reactor coolant to the nuclear fission module 30 along the coolant flow path or fluid stream indicated by the arrow 140 indicating the direction. do. The primary coolant then continues along the coolant flow path 140 and through the open end 390 formed in the lower support plate 370.

As described above, regardless of the configuration selected for the nuclear fission core 20, it is important to remove heat generated by the nuclear fission core 20 and the nuclear fission module 30 therein. Proper heat removal is important for several reasons. For example, if the peak temperature exceeds the material limit, thermal damage to the reactor core structure material may occur. Such peak temperature may undesirably shorten the working life of the structure exposed to the peak temperature by changing the mechanical properties of the structure, in particular by changing the properties associated with the thermal creep. In addition, reactor power density is limited by the ability of the core structural material to withstand high peak temperatures without damage. Alternatively, the nuclear fission system 10 may be used to perform a test, such as a test to determine the effect of temperature on the reactor material. Controlling the reactor core temperature by appropriately controlling the heat from the reactor core is important for the successful execution of such tests.

It would also be desirable to achieve a uniform flow rate of heat transfer fluid through the intermediate heat exchanger 150. Such a uniform flow rate will prevent uneven coolant flow to the reactor core and the resulting core reactivity fluctuations. It would also be desirable to provide a uniform flow distribution of coolant through the heat exchanger in order to avoid a differential flow of coolant through the heat exchanger. Preventing uneven flow of coolant may mitigate the occurrence of "hot spots" of local temperature in the heat exchanger. Such local temperature "hot spots" may shorten the operating life of the heat exchanger. In addition, the uniform flow acts to improve uniform heat exchange across the heat transfer surface of the heat exchanger, thereby improving heat exchange for a given heat exchange region. The construction and operation of the intermediate heat exchanger 150 alleviates this concern.

The structure of the intermediate heat exchanger 150 will now be described. 1, 7, 8, 8A, and 9, the intermediate heat exchanger 150 includes a heat exchanger body 420 attached to the inner wall surface 122 of the pressure vessel 120. Thus, the intermediate heat exchanger 150 is supported in the pressure vessel 120. As an alternative, the inner wall surface 122 forming the pool 125 may form the rear wall of the intermediate heat exchanger 150. The heat exchanger body 420 includes an upright, entirely L-shaped (in cross-section) rear portion 425, which rearwards the primary fluid discharge plenum volume or discharge plenum chamber 430 therein. Form. As such, the primary fluid discharge plenum chamber 430 becomes part of the heat exchanger body 420. As described in more detail below, the primary fluid discharge plenum chamber 430 is formed to provide uniform flow of a first heat transfer fluid (ie, primary heat transfer fluid) through the primary fluid discharge plenum chamber 430. do. A primary fluid discharge port 435 is formed from the rear portion 425 of the heat exchanger body 420, but within the primary fluid discharge plenum chamber 430, the primary fluid discharge port being the primary loop coolant pipe 130. Open into). The bottom portion 440 of the heat exchanger body 420, which forms a bottom plenum 450 for high temperature secondary sodium, is connected to the rear portion 425. The bottom plenum 450 having a bottom plenum discharge side or port 455 has a box-shaped structure having a top surface 460 to which a plurality of upright plate-type heat transfer members 470 are integrally attached by welding or the like. To form. Each heat transfer member 470 penetrates through a flow channel 460 having an inlet 490 and an outlet 500 at each end. Inlet 490 is in fluid communication with the heat transfer fluid flowing through cold leg pipe segment 200. Outlet 500 is in fluid communication with the heat transfer fluid in bottom plenum 450. It will also be appreciated that primary fluid can be supplied to the heat exchanger body 420 without the use of conduits or manifolds. In other words, the primary fluid is supplied to the heat exchanger body 420 without conduits or without manifolds. It will be appreciated that the pool 125 may also have no manifold. It will also be appreciated that the inlet side of the intermediate heat exchanger 150 may not have a manifold and the outlet side of the intermediate heat exchanger 150 may not have a manifold. This may reduce the capital cost required to build the reactor 10 and / or the capital cost of manufacturing the heat exchanger 150 because no such conduit or manifold is required.

8, 8A, and 9, the intermediate heat exchanger 150 includes a plurality of adjacent heat transfer members 470. The plurality of adjacent heat transfer members 470 are spaced apart by a relatively small predetermined distance “d” to form a plurality of flow passages 510 between adjacent heat transfer members 470. The distance "d" is the distance required to achieve a uniform flow distribution between the flow passages 510. In other words, the heat transfer members 470 are spaced apart by a distance “d” to uniformly distribute the flow of the primary heat transfer fluid through the plurality of flow passages 510. In order to achieve a uniform distribution of the flow of the primary heat transfer fluid through the plurality of flow passages, the distance between adjacent heat transfer members 470, if necessary, to have different values for different reactor core configurations. ") Can be designed. This is because a special reactor core configuration can have an in-core (in-core) structure that alters or hinders the free flow of the primary heat transfer fluid as the heat transfer fluid is moved towards the heat exchanger 150. It is true. To compensate for this effect, the distance "d" may be designed to have different values. In another embodiment, the heat exchanger body 420 may include a guide structure 515 for guiding the flow of heat transfer fluid into the heat exchanger 150. Guide structure 515 suitably spans heat transfer members 470 and is associated with flow passage 510 such that heat transfer fluid is guided into flow passage 510. The heat exchanger body 420 further includes an upper portion 520 sealingly mounted or connected to the upper portion of the plurality of heat transfer members 470 and the upper portion of the rear portion 425. In order to receive the cooled secondary sodium flowing along the flow path 532 from the steam generator 210, the upper portion 520 forms an upper plenum 530 therein. The cooled secondary sodium flowing along flow path 532 and the primary heat transfer fluid flowing along flow path 140 form a cross flow flow configuration. In this crossflow flow configuration, flow path 532 is substantially perpendicular to flow path 140 in intermediate heat exchanger 150 (ie, plus or minus 45 °). To allow cooled secondary sodium to flow through inlet 490, into flow channel 470, through outlet 500, and into bottom plenum 450, top plenum 530 is defined as an inlet. In fluid communication with 490.

9A and 9B, in an alternate embodiment, the intermediate heat exchanger 150 includes a cold leg pipe segment 200, and the cooled secondary heat transfer fluid flows through the cold leg pipe segment 200. Flow along the path 532. In this regard, the cooled secondary heat transfer fluid enters the plate member 534 through the opening 536a and exits the opening 536b formed in the plate member 534. The secondary heat transfer fluid continues along the flow path 532 and flows into the return pipe segment 538 for returning the secondary heat transfer fluid to the steam generator 210. The cooled secondary sodium flowing along the path 532 and the primary heat transfer fluid flowing along the path 140 form a countercurrent flow configuration. In this countercurrent flow configuration, the flow path 532 is parallel to the flow path 140 in the intermediate heat exchanger 150, but in opposite directions.

9C and 9D, in an alternative embodiment, the intermediate heat exchanger 150 includes a cold leg pipe segment 200, and the cooled secondary heat transfer fluid flows through the cold leg pipe segment 200. Flow along the path 532. In this regard, the cooled secondary heat transfer fluid enters the plate member 534 through the opening 536a and exits the opening 536b formed in the plate member 534. The secondary heat transfer fluid continues along the flow path 532 and flows into the return pipe segment 538 for returning the secondary heat transfer fluid to the steam generator 210. The cooled secondary heat transfer fluid flowing along the path 532 and the primary heat transfer fluid flowing along the path 140 form a cocurrent flow configuration. In this cocurrent flow configuration, the flow path 532 is parallel and in the same direction with respect to the flow path 140 in the intermediate heat exchanger 150.

10, 11, 12, and 13, an alternative embodiment for heat transfer member 470 is shown. In this regard, at least one of the plurality of heat transfer members 470 includes a wall 540, which wall includes an enhanced heat transfer surface 550 that receives a flow of primary heat transfer fluid along the enhanced heat transfer surface 550. To form. In this regard, the wall 540 separates the hot primary sodium (ie, the first heat transfer fluid) from the cold secondary sodium (ie, the second heat transfer fluid). One or more of the plurality of heat transfer members 470 include one or more integrally connected outer fins or outer flanges 560 extending outward from the wall 540 to form an enhanced heat transfer surface 550. The outer flange 560 improves heat transfer by increasing the surface area for increased heat transfer. Instead, one or more of the plurality of heat transfer members 470 includes one or more nodules 570 that protrude outward from the wall 540 to form an enhanced heat transfer surface 550. The nodule 570 improves heat transfer by increasing the surface area for increased heat transfer. As another alternative, one or more of the plurality of heat transfer members 470 includes one or more integrally connected inner fins or inner flanges 580 extending inwardly from the wall 540 for enhanced heat transfer. Inner flange 580 improves heat transfer by increasing surface area for increased heat transfer. As another alternative, one or more of the plurality of heat transfer members 470 includes one or more conduits 590 extending along flow channel 490 to receive flow through conduits 590 of cooled heat transfer fluid. .

13A and 13B illustrate additional embodiments that include an enhanced heat transfer surface 550. In this regard, the outer flange 560 may have a heat transfer surface that increases gradually as the outer flange 560 extends from the front portion 592 of the wall 540 to the rear portion 594 of the wall 540. will be. As will be appreciated by those skilled in the art of thermodynamics, a greater portion of heat transfer will occur near the front portion 592 of the wall 540 than near the rear portion 594 of the wall 540, which is the primary. This is because heat transfer fluid flows from the front portion 592 of the wall 540 to the back portion 594 of the wall 540. Thus, closer to the front portion 592 of the wall 540 will result in more heat transfer, and closer to the rear portion 594 of the wall 540 will result in less heat transfer. To compensate for the reduced heat transfer near the rear portion 594 of the wall 540, the flange 560 extends from the front portion 592 of the flange 560 to the rear portion 594 of the flange 560. The flange 560 has a heat transfer surface area that increases gradually as it is extended. For example, the flange 560 may have a wedge-shape having fewer end portions near the front portion 592 and wider end portions near the rear portion 594. As another alternative, the density of the nodule 570 protruding outward from the wall 540 (ie, the number of nodules 570 per unit area) can be increased from the front portion 592 to the rear portion 594. It will increase the heat transfer surface area from the front portion 592 of the wall 540 to the rear portion 594 of the wall 540. This configuration of the nodule 570 compensates for reduced heat transfer in proximity to the back portion 594 of the wall 540.

Referring now to FIGS. 14 and 15, an alternative embodiment of a nuclear fission system 10 is shown where a plurality of heat exchangers, such as first heat exchanger 600 and second heat exchanger 610, are shown. It is. Each of the first heat exchanger 600 and the second heat exchanger 610 is a first low temperature leg pipe segment 620a for supplying a cooled heat transfer fluid to the first heat exchanger 600 and the second heat exchanger 610. And a second low temperature leg pipe segment 620b to each of the steam generators 210. Each of the first heat exchanger 600 and the second heat exchanger 610 may allow a first hot leg pipe segment 630a to allow extraction of heated heat transfer fluid from the first heat exchanger 600 and the second heat exchanger 610. And the second high temperature leg pipe segment 630b are each coupled to the steam generator 210. Also, if desired, for the reasons described, the first shut-off valve 640a installed in the first low temperature leg pipe segment 620a and the second shutoff valve installed in the second low temperature leg pipe segment 620b. There may be 640b. Also for reasons described, there may be a third shutoff valve 650a installed in the first high temperature leg pipe segment 630a and a fourth shutoff valve 650b provided in the second high temperature leg pipe segment 630b. In this regard, if desired, the shutoff valves 640a / 640b can be closed to stop coolant flow into and out of the first heat exchanger 600 and thereby isolate the first heat exchanger 600. . Also, if desired, the shutoff valves 640a / 640b can be closed to stop the flow of coolant into and out of the second heat exchanger 610 and thereby isolate the second heat exchanger 610. If a leak occurs within the wall 540 of any heat transfer member 470, it may be desirable to isolate the first heat exchanger 600 or the second heat exchanger 610. In addition, a plurality of pumps, such as pumps 660a and 660b, are used to pump the cooled heat transfer fluid from the heat exchangers 600 and 610 to the core 20 with the nuclear fission, respectively. Coupled to the group.

Referring to FIG. 16, one embodiment is shown where a plurality of heat exchangers 670a, 670b, 670c, 670d, 670e, 670f and 670g are side by side around the inner wall surface 122 of the pressure vessel 120. Or aligned adjacently. This embodiment provides another configuration for using the intermediate heat exchanger 150.

1, 6, 7, 8, 8a, 9, 10, 11, 12, and 13, the operation of the intermediate heat exchanger 150 will be further described. In this regard, due to the fission process, the heat generated by the fuel rod 50 in the nuclear fission furnace core 20 is absorbed by the primary heat transfer fluid (also referred to herein as the first heat transfer fluid). As heat is generated, the first pump 170 is actuated to suck or draw the first heat transfer fluid from the intermediate heat exchanger 150 and then to pass the first heat transfer fluid past the fuel rod 50 to the upper core support plate 400. Pump into the coolant pool 125 through the flow slot 410 within. Subsequent operation of the first pump 170 will then draw the first heat transfer fluid through the flow passage 510 and into the primary fluid discharge plenum chamber 430. As the first heat transfer fluid flows through the flow passage 510, the first heat transfer fluid will be in intimate contact with the enhanced heat transfer surface 550. As the first heat transfer fluid flows in intimate contact with the enhanced heat transfer surface 550, a lower temperature secondary heat transfer fluid flows from the steam generator 210, along the cold pipe segment 200, to the top plenum 530. Inwards, through inlet 490, through flow channel 480, through outlet 500, and into bottom plenum 450. Thereafter, the second heat transfer fluid is received by the hot leg pipe segment 190, which exits the lower plenum 450 through the discharge port 455 and passes through the steam generator 210. The second heat transfer fluid moving along a portion of the hot leg pipe segment 190 and passing through the steam generator 210 transfers its heat to the body of water 230 to produce steam 240. The second pump 220 is operated to deliver cold secondary fluid from the steam generator 210 to the upper plenum 520.

Continuing with reference to FIGS. 1, 6, 7, 8, 8a, 9, 10, 11, 12, and 13, flow channel 480 from the first hotter heat transfer fluid flowing through flow passage 510 is described. Heat is transferred to the second, lower temperature heat transfer fluid flowing through it. This heat transfer is accomplished by conduction through the wall 540 of the heat transfer member 470.

1, 6, 7, 8, 8a, 9, 10, 11, 12, and 13, in order to uniformly distribute the flow of the primary heat transfer fluid through the plurality of flow passages 510, Adjacent heat transfer members 470 are spaced apart by the predetermined distance “d” described above. As described above, the primary fluid discharge plenum chamber 430 is formed to provide uniform flow of the first heat transfer fluid (ie, primary heat transfer fluid) through the primary fluid discharge plenum chamber 430. In this regard, an upper portion of the primary fluid discharge plenum chamber 430 is disposed proximate to the inner wall surface 122, such that the upper portion of the primary fluid discharge plenum chamber 430 is a primary fluid discharge plenum chamber 430. Less volume than the lower portion of 430. In other words, the volume of the primary fluid discharge plenum chamber 430 becomes larger the closer to the discharge port 435 than the inlet 490. This shape of the primary fluid discharge plenum chamber 430 provides a uniform flow of first heat transfer fluid (primary heat transfer fluid) through the primary fluid discharge plenum chamber 430.

Illustrative  Way

Illustrative methods relating to exemplary embodiments of nuclear fission systems and heat exchangers are now described.

With reference to FIGS. 17-47, an illustrative method for use in connection with a nuclear fission furnace that may generate heat is provided for heat exchanger assembly.

Referring to FIG. 17, an illustrative method 680 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 690. At block 700, the method includes receiving a heat exchanger body. At block 710, means for removing heat is coupled to the heat exchanger body. Such method ceases at block 720.

Referring to FIG. 18, an illustrative method 680 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 740. At block 750, the method includes receiving a heat exchanger body. At block 760, the method includes coupling a means for removing heat to the heat exchanger body. At block 770, the method includes coupling heat removal means configured to achieve a predetermined flow of heat transfer fluid into the heat exchanger body. Such method ceases at block 780.

Referring to FIG. 19, an illustrative method 790 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 800. At block 810, the method includes receiving a heat exchanger body. At block 820, the method includes coupling a means for removing heat to the heat exchanger body. At block 830, the method includes coupling heat removal means configured to achieve a predetermined flow of heat transfer fluid into the heat exchanger body. At block 840, heat removal means coupled to achieve a substantially uniform flow of heat transfer fluid into the heat exchanger body is coupled. Such method ceases at block 850.

Referring to FIG. 20, an illustrative method 860 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 870. At block 880, the method includes receiving a heat exchanger body. In block 890, means for removing heat is coupled to the heat exchanger body. At block 900, heat removal means having an enhanced heat transfer surface are coupled. Such method stops at block 910.

Referring to FIG. 21, an illustrative method 920 of assembling a heat exchanger for use in connection with a full-type nuclear fission furnace begins at block 930. At block 940, means for removing heat is coupled to the heat exchanger body. At block 950, a heat exchanger body is received that defines a plenum volume of a predetermined shape therein to achieve a substantially uniform flow of heat transfer fluid through the heat exchanger body. Such method stops at block 970.

Referring to FIG. 21A, an illustrative method 971 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 973. At block 975, the method includes receiving a heat exchanger body. At block 997, means for removing heat is coupled to the heat exchanger body. In block 978, a heat exchanger body without a manifold is received. Such method ceases at block 979.

Referring to FIG. 22, an illustrative method 980 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 990. At block 1000, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. Such method ceases at block 1010.

Referring to FIG. 22A, an illustrative method 1011a of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1013a. At block 1015a, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. In block 1017a a guide structure for guiding the flow of pool fluid is received. Such method ceases at block 1019a.

Referring to FIG. 22B, an illustrative method 1011b of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1013b. At block 1015b, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. At block 1017b, a guide structure for guiding the flow of pool fluid is received. In block 1018b, a guide structure is received that is configured to achieve a substantially uniform flow of pool fluid within at least a portion of the heat exchanger body. Such method ceases at block 1019b.

Referring to FIG. 22C, an illustrative method 1011c of assembling a heat exchanger for use in connection with a full-type nuclear fission furnace capable of generating heat begins at block 1013c. At block 1015c, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. In block 1017c, a heat exchanger body is received having an inlet guide structure for guiding the inlet flow of pool fluid. Such method ceases at block 1019c.

Referring to FIG. 22D, an illustrative method 1011d of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1013d. At block 1015d, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. In block 1017d, a heat exchanger body is received having an outlet guide structure for guiding the outlet flow of pool fluid. Such method ceases at block 1019d.

Referring to FIG. 22E, an illustrative method 1011e of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1013e. At block 1015e, such a method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. In block 1017e, a guide structure is received to prevent pool fluid from contacting the pool wall, and the pool fluid is disposed within at least a portion of the heat exchanger body. Such method ceases at block 1019e.

Referring to FIG. 23, an illustrative method 1020 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1030. At block 1040, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. In block 1050, the vessel is received with a reaction defining a portion of the outlet plenum volume of non-uniform shape. Such method stops at block 1060.

Referring to FIG. 24, an illustrative method 1070 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1080. At block 1090, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. At block 1100, a heat exchanger body is received in which the heat exchanger body can heat transfer communicate with the core by nuclear fission. Such method ceases at block 1110.

Referring to FIG. 25, an illustrative method 1120 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1130. At block 1140, the method includes receiving a heat exchanger body having a surface defined for a portion of the plenum volume. At block 1150, the method includes receiving a heat exchanger body without a manifold. Such method ceases at block 1160.

Referring to FIG. 26, an illustrative method 1170 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1180. At block 1190, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1200, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. Such method ceases at block 1210.

Referring to FIG. 27, an illustrative method 1220 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1230. At block 1240, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1250, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1260, a heat transfer member configured to achieve a predetermined flow of heat transfer fluid into the heat exchanger body is coupled. Such method ceases at block 1270.

Referring to FIG. 28, an illustrative method 1280 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1290. At block 1300, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1310, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1320, a heat transfer member configured to achieve a predetermined flow of heat transfer fluid into the heat exchanger body is coupled. At block 1330, a heat transfer member is coupled that is configured to achieve a substantially uniform flow of heat transfer fluid into the heat exchanger body. Such method ceases at block 1340.

Referring to FIG. 29, an illustrative method 1350 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1360. At block 1370, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of which is part of the plenum volume. A defining surface is formed on the heat exchanger body. At block 1380, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1390, a heat transfer member having a conduit extending along the flow channel is coupled. Such method ceases at block 1400.

Referring to FIG. 30, an illustrative method 1410 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1420. At block 1430, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1440, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1450, a heat exchanger body is received that is in heat transfer communication with the core by nuclear fission. Such method ceases at block 1460.

Referring to FIG. 31, an illustrative method 1470 of assembling a heat exchanger for use in connection with a full-type nuclear fission furnace capable of generating heat begins at block 1480. At block 1490, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. In block 1500, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1510, a heat exchanger body is received that is capable of heat transfer communication with the core by traveling wave nuclear fission. At block 1515, a heat exchanger body is received that is in heat transfer communication with the core by traveling wave nuclear fission. Such method ceases at block 1520.

Referring to FIG. 32, an illustrative method 1521 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1523. At block 1525, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. In block 1527, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1528, a heat exchanger body without a manifold is received. Such method ceases at block 1529.

Referring to FIG. 33, an illustrative method 1530 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1540. At block 1550, such a method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1560, a heat transfer member is coupled to the heat exchanger body, the heat transfer member penetrating through the flow channel. At block 1570, a heat transfer member having a wall on which an enhanced heat transfer surface is formed is coupled. Such method ceases at block 1580.

Referring to FIG. 34, an illustrative method 1650 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1660. At block 1670, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. In block 1680, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. Such method ceases at block 1690.

Referring to FIG. 35, an illustrative method 1700 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1710. At block 1720, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, wherein the portion of the plenum volume is received. A defining surface is formed on the heat exchanger body. In block 1730, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 1740, a plurality of adjacent heat transfer members are connected that are configured to achieve uniform flow of heat transfer fluid into the heat exchanger body. Such method ceases at block 1750.

Referring to FIG. 36, an illustrative method 1760 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1770. At block 1780, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1790, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 1800, a vessel is received in response to define a portion of the outlet plenum volume of non-uniform shape. Such method ceases at block 1810.

Referring to FIG. 37, an illustrative method 1820 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1830. At block 1840, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1850, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 1860, a heat exchanger body is received that can be in heat transfer communication with the core with nuclear fission. Such method ceases at block 1870.

Referring to FIG. 38, an illustrative method 1880 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1890. In block 1900, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 1910, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 1915, a heat exchanger body is received that can be in heat transfer communication with the core by nuclear fission. In block 1920, a heat exchanger body is received which is in heat transfer communication with the core with traveling wave nuclear fission. Such method ceases at block 1930.

Referring to FIG. 39, an illustrative method 1940 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 1950. In block 1900, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. In block 1970, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 1980, two or more heat transfer fluids having a crossflow flow orientation are received. Such method ceases at block 1990.

Referring to FIG. 40, an illustrative method 2000 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2010. At block 2020, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a desired flow of heat transfer fluid into the plenum volume, defining a portion of the plenum volume. Is formed on the heat exchanger body. At block 2030, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2040, two or more heat transfer fluids with countercurrent flow orientations are received. Such method ceases at block 2050.

Referring to FIG. 41, an illustrative method 2060 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2070. At block 2080, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of which is part of the plenum volume. A defining surface is formed on the heat exchanger body. At block 2090, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2100, two or more heat transfer fluids having a cocurrent flow orientation are received. Such method ceases at block 2110.

Referring to FIG. 42, an illustrative method 2120 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2130. At block 2140, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 2150, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2160, one or more of the plurality of adjacent heat transfer members having a wall on which an enhanced heat transfer surface is formed to enhance heat transfer through the wall is coupled. Such method ceases at block 2170.

Referring to FIG. 43, an illustrative method 2180 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2190. At block 2200, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of which is part of the plenum volume. A defining surface is formed on the heat exchanger body. In block 2210, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2220, one or more of a plurality of adjacent heat transfer members having a wall with an enhanced heat transfer surface formed thereon to enhance heat transfer through the wall. At block 2230, one or more of the plurality of adjacent heat transfer members having a flange extending outwardly from the wall to form an enhanced heat transfer surface is coupled. Such method ceases at block 2240.

Referring to FIG. 44, an illustrative method 2250 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2260. At block 2270, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of which is part of the plenum volume. A defining surface is formed on the heat exchanger body. At block 2280, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2290, one or more of the plurality of adjacent heat transfer members having a wall on which an enhanced heat transfer surface is formed to enhance heat transfer through the wall is coupled. At block 2300, one or more of the plurality of adjacent heat transfer members having a flange extending inwardly from the wall to form an enhanced heat transfer surface is coupled. Such method ceases at block 2310.

Referring to FIG. 45, an illustrative method 2320 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2330. At block 2340, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of the plenum volume being defined. A defining surface is formed on the heat exchanger body. At block 2350, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2360, one or more of the plurality of adjacent heat transfer members having a wall with an enhanced heat transfer surface formed thereon to enhance heat transfer through the wall. At block 2370, one or more of the plurality of adjacent heat transfer members having nodules protruding outward from the wall are coupled to form an enhanced heat transfer surface. Such method ceases at block 2380.

Referring to FIG. 46, an illustrative method 2390 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2400. At block 2410, the method includes receiving a heat exchanger body that defines a plenum volume therein shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of which is part of the plenum volume. A defining surface is formed on the heat exchanger body. At block 2420, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2430, a heat transfer member is coupled having a conduit extending along the flow channel for the flow of the second heat transfer fluid through the conduit. Such method ceases at block 2440.

Referring to FIG. 47, an illustrative method 2450 of assembling a heat exchanger for use in connection with a full-type nuclear fission reactor capable of generating heat begins at block 2460. At block 2470, the method includes receiving a heat exchanger body defining therein a plenum volume shaped for a predetermined flow of heat transfer fluid into the plenum volume, the portion of which is part of the plenum volume. A defining surface is formed on the heat exchanger body. At block 2480, a plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of flow passages are formed between the heat transfer members facing each other among the plurality of adjacent heat transfer members to heat transfer through the plurality of flow passages. Spaced by a predetermined distance to distribute the flow of the fluid. At block 2490, a heat exchanger body without a manifold is received. Such method ceases at block 2500.

Those skilled in the art will understand that the components (e.g., tasks), devices, objects and descriptions incorporating the description herein are used as examples for conceptual clarity, and that changes in various configurations It will be understood that it can be done. As a result, as used herein, the description of specific examples and accompanying descriptions are intended to represent their more general classes. In general, the use of any particular example is intended to illustrate that kind and the exclusion of certain components (eg, operations), devices, and purposes should not be considered limiting.

In addition, those of ordinary skill in the art will appreciate that the specific exemplary processes and / or apparatuses and / or techniques described above may be taught in various parts of this application, for example, in the claims filed and / or in several places herein. And / or device and / or technology.

While particular aspects of the subject matter described herein have been shown and described, those of ordinary skill in the art, based on the teachings herein, will readily appreciate that changes and modifications can be made without departing from the subject matter described herein and its broader aspects. It is to be understood that the appended claims, therefore, cover all such changes and modifications as fall within the true spirit and scope of the subject matter described herein. Those skilled in the art will generally appreciate that the terms used herein and in particular the terms used in the claims (eg, the text of the appended claims) are generally "open" terms (eg, " The term "comprise" is to be interpreted as "including but not limited to" and the term "having" to be "having at least" and "comprising" to be "including but not limited to" and the like. It is to be understood that one of ordinary skill in the art, if a certain number of claim recitations are intended, will be explicitly enumerated in the claims, and without such an enumeration no such intent is present. For the sake of clarity, for example, the following appended claims are claimed to claim recitation. It may include the use of an introductory phrase of “one or more” and “one or more” to introduce a term, but the use of such phrase may refer to the same claim as “one or more” or “one or more”. Even if it includes an introductory phrase and an indefinite article (such as "a" or "an"), any introduction of claim enumeration by an indefinite article ("a" or "an") includes any such introduced claim enumeration. It should not be construed as meaning that a particular claim is limited to claims that contain only one such enumeration; the same applies when using an indefinite article to introduce a claim enumeration. Although the claims enumerations are expressly described, those skilled in the art should interpret that enumerations generally mean at least the number stated. It will be appreciated (for example, a pure enumeration of “two enumerations”, typically, means two or more enumerations, or more than two or more enumerations, without other modifications). And where conventions similar to one or more of "C, etc." are used, such constructs are generally intended in the sense that those skilled in the art can understand as a set (e.g., of "A, B, and C A system having at least one "refers to a system having A alone, B alone, C alone, A and B together, A and C together, B and C together, and / or A, B, and C together, and the like. Include, but are not limited to such systems). Where a set similar to “at least one of A, B, or C, etc.” is used, such a construct is generally intended in the sense that one of ordinary skill in the art would understand it as a set (eg, “A, B, or A system having at least one of C "refers to A alone, B alone, C alone, A and B together, A and C together, B and C together, and / or A, B, and C together, etc. Branches will include, but are not limited to such systems). Unless stated otherwise in the context, a phrase that typically refers to a separate word and / or two or more other terms, regardless of whether it is described in the description, claims, or in the figures, is one of the terms, It will be understood by those skilled in the art that the intention is to consider the possibility of either or both of the terms being included. For example, it will be understood that "" A or B "typically includes the possibility of" A "or" B "or" A and B ".

In the context of the appended claims, those skilled in the art will appreciate that the enumerated operations may be generally performed in any order. In addition, although various operational flows are presented in sequence (s), it should be understood that the various tasks may be performed in a different order than that described, or that they may be performed concurrently. something to do. Unless otherwise stated in the context, examples of such other sequences include superposition, interleave, abort, rearrangement, incremental, preparatory, supplemental, concurrent, opposite, or many other variations. Will include the order. Also, unless otherwise indicated in the context, terms such as "responsive" "related" or other past tense adjectives generally do not exclude such modifications.

Thus, a heat exchanger, a method for this heat exchanger and a nuclear fission furnace system are provided.

While various aspects and embodiments have been described herein, other aspects and embodiments will be apparent to those skilled in the art. For example, referring to FIG. 14, shutoff valves 640a / 640b / 650a / 650b are each in each one of a plurality of thermocouples (not shown) disposed in pipe 620a / 620b / 630a / 630b. May be coupled. Depending on the temperature of the heat transfer fluid introduced into and out of the heat exchanger 600/610, the control member may selectively and gradually open and close the shutoff valves. That is, the amount of heat transfer required in the heat exchanger as a function of temperature sensed by the thermocouple may be preprogrammed into the control and stored in the control. The temperature in the heat exchangers can be detected by the control unit through the thermocouples, and the control unit gradually opens the shutoff valves so that the heat transfer occurring in the heat exchangers is substantially consistent with the programmed values stored in the control unit. And the shutoff valve can be operated by closing. In this way, by allowing the control to automatically adjust the valves, the heat exchanger 600/610 may be selectively operated so that the correct amount of heat transfer can be provided within the heat exchangers.

In addition, the various aspects and embodiments described herein are for illustrative purposes and are not limiting, the true scope and spirit of which is to be determined by the claims that follow. In addition, in the following claims, the corresponding structures, materials, acts and equivalents of all means or steps including functional components may be combined with other claimed components as specifically claimed to perform those functions. Will include any structure, material, or operation.

Claims (22)

A method of assembling a heat exchanger that can be placed in a pool fluid present in a pool-type nuclear fission reactor for use in connection with a pool-type nuclear fission reactor:
The heat exchanger may be disposed proximate to the inner circumference of the pool wall confining the pool fluid, the method comprising:
Receiving a heat exchanger body having a surface defining a portion of the plenum volume
Heat exchanger assembly method comprising a. 19. The method of claim 1 or 12 or 18, wherein a portion of the plenum volume defined by the surface formed on the heat exchanger body may be occupied by heat transfer fluid. 19. The method of claim 1 or 12 or 18, wherein a portion of the plenum volume defined by the surface formed on the heat exchanger body is capable of controlling the flow of heat transfer fluid. The method of claim 1, wherein a portion of the plenum volume defined by the surface formed on the heat exchanger body has a predetermined shape for guiding flow of pool fluid through the heat exchanger body. 13. The method of claim 1 or 12, wherein the surface formed on the heat exchanger body forms a portion of an inlet manifold associated with a portion of the plenum volume. 13. The method of claim 1 or 12, wherein the surface formed on the heat exchanger body forms a portion of an outlet manifold associated with a portion of the plenum volume. 10. The method of claim 1, wherein receiving the heat exchanger body includes receiving a guide structure for guiding the flow of pool fluid. 2. The method of claim 1, wherein receiving the heat exchanger body comprises receiving a heat exchanger body having an inlet guide structure for guiding the inlet flow of pool fluid. 2. The method of claim 1, wherein receiving the heat exchanger body comprises receiving a heat exchanger body having an outlet guide structure for guiding the outlet flow of pool fluid. 2. The method of claim 1 wherein the surface formed on the heat exchanger body has increased heat transfer. 13. The method of claim 1 or 12, wherein receiving the heat exchanger body comprises receiving a heat exchanger body without a manifold. A method of assembling a heat exchanger that can be placed in a pool fluid present in a pool-type nuclear reactor for use in connection with a pool-type nuclear reactor that can generate heat, wherein the heat exchanger is internal to the pool wall that traps the pool fluid. Can be arranged in close proximity to the perimeter, the method comprising:
(a) receiving a heat exchanger body therein defining a plenum volume in the shape for a predetermined flow of heat transfer fluid into the plenum volume, the heat exchanger body having a surface defining a portion of the plenum volume; Receiving a heat exchanger body; And
(b) coupling a heat transfer member to the heat exchanger body, the coupling step forming a flow channel therethrough;
Heat exchanger assembly method comprising a. 13. The method of claim 12, wherein coupling the heat transfer member comprises coupling a heat transfer member configured to achieve a predetermined flow of heat transfer fluid into the heat exchanger body. 13. The method of claim 12, wherein coupling the heat transfer member comprises coupling a heat transfer member having a conduit extending along the flow channel. 19. The method of assembling a heat exchanger according to claim 12 or 18, wherein the heat exchanger body includes an inlet side, and the inlet side is free of a manifold. 19. The method of claim 12 or 18, wherein the heat exchanger body includes an outlet side, the outlet side having a manifold. 13. The method of claim 12, wherein coupling the heat transfer member comprises coupling a heat transfer member having a wall on which an enhanced heat transfer surface is formed. A method of assembling a heat exchanger that can be placed in a pool fluid present in a pool-type nuclear reactor for use in connection with a pool-type nuclear reactor that can generate heat, wherein the heat exchanger is internal to the pool wall that traps the pool fluid. Can be arranged in close proximity to the perimeter, the method comprising:
(a) receiving a heat exchanger body having a surface that defines a portion of the plenum volume that is shaped for a predetermined flow of heat transfer fluid into the plenum volume; And
(b) connecting a plurality of adjacent heat transfer members to the heat exchanger body.
Wherein the plurality of adjacent heat transfer members comprises a predetermined distance to form a plurality of flow passages between opposing heat transfer members among the plurality of adjacent heat transfer members to distribute the flow of heat transfer fluid through the plurality of flow passages. Heat exchanger assembly method that will be spaced apart. 19. The method of claim 18, wherein connecting the plurality of adjacent heat transfer members comprises connecting a plurality of adjacent heat transfer members configured to achieve a substantially uniform flow of heat transfer fluid into the heat exchanger body. How to assemble a heat exchanger. 19. The method of claim 18, further comprising receiving a reactor vessel coupled to the heat exchanger body, wherein the reactor vessel defines a portion of the outlet plenum volume of non-uniform shape. . 19. The method of claim 18, wherein joining the plurality of adjacent heat transfer members is selected from cross-flow orientation, counter-flow orientation, and parallel-flow orientation. Connecting a plurality of adjacent heat transfer members to receive two or more heat transfer fluids having an orientation. 19. The method of claim 18, wherein connecting the plurality of adjacent heat transfer members comprises connecting at least one of the plurality of adjacent heat transfer members having a wall formed with an enhanced heat transfer surface for enhanced heat transfer through the wall. Heat exchanger assembly method.

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