JP2013506131A - Heat exchanger, method thereof and fission reactor system - Google Patents

Abstract

  The present invention is a heat exchanger, method thereof and fission reactor system. The heat exchanger includes a heat exchanger body that defines an outlet plenum chamber formed therein for a constant flow rate of hot first heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced by a predetermined distance that defines a plurality of flow paths between the heat transfer members. The flow path opens into the outlet plenum chamber. A predetermined distance space of the heat transfer member uniformly distributes the first heat transfer fluid through the flow path so as to enter the outlet plenum chamber beyond the surface of the heat transfer member. Each heat transfer member defines a flow path therethrough for the heat transfer member of the colder second heat transfer fluid. Since the first heat transfer fluid flows through the chamber and the second heat transfer fluid flows through the flow path at the same time, heat transfer occurs from the hot heat transfer fluid to the cooler second heat transfer fluid. .

Description

Detailed Description of the Invention

[Cross-reference with related applications]
This application relates to the following list of applications ("Related Applications") and claims the earliest available effective filing date benefit from them (eg, the earliest available priority date other than provisional applications) Or claim the benefit under 35 USC 119 (e) of any provisional application of any related application, any and all patents, grandparents, great-grandparents, etc.). The subject matter of related applications and related application provisional applications, any and all patents, grandparents, great-grandparents, etc., are hereby incorporated by reference to the extent that the subject matter does not conflict here.

[Related applications]
For the purposes of the USPTO's special statutory requirements, this application is based on US patent application 12 / 586,741, entitled “Heat Exchanger, Method and Fission Reactor System”, inventor Jon D. McWhirter, 2009. An application that constitutes a continuation-in-part application filed on September 25, currently pending at the Office, or that is currently pending and that gave the benefit of the filing date.

  For the purposes of the USPTO's special statutory requirements, this application is based on US patent application 12 / 653,656, entitled “Heat Exchanger, Method and Fission Reactor System”, inventor Jon D. McWhirter, 2009. An application that constitutes a continuation-in-part of an application filed on Dec. 15 and is currently pending at the Office, or an application that is currently pending that has been granted the benefit of the filing date.

  For the purposes of the USPTO's special statutory requirements, this application is based on US patent application 12 / 653,653, entitled “Heat Exchanger, Method and Fission Reactor System”, inventor Jon D. McWhirter, 2009. An application that constitutes a continuation-in-part of an application filed on Dec. 15 and is currently pending at the Office, or an application that is currently pending that has been granted the benefit of the filing date.

  The United States Patent Office (USPTO) has published a notice that a USPTO computer program requires that a patent application state a serial number and indicate that the application is a continuation or partial continuation application. Stephen G. Kunin, Profit of Prior Application, USPTO Official Gazette, March 18, 2003, http: // www. uspto. gov / web / offices / com / sol / og / 2003 / week11 / patbene. Available at htm. The application entity of the present application (hereinafter “applicant”) specifically refers to the application for which priority is claimed as listed by law. Applicant understands that the statute is clear in a particular reference language, and in order to claim priority to a U.S. patent application, any feature such as serial number or “continuation application” or “partial continuation application” Understand that neither of them is needed. Regardless, the Applicant understands that the USPTO computer program requires some data input, from which Applicant represents this application as a continuation-in-part of the above parent application. However, such an indication shall not be construed in any way as any form of comment and / or recognition as to whether this application contains new matter added to the subject matter of the parent application. Is clearly shown.

[Background Technology]
This application relates generally to induced nuclear reactions and includes systems, processes, and elements that implement such processes. The element can be a nuclear core, a first heat exchanger or a pump, etc., immersed in a liquid coolant in the vessel. More particularly, it relates to a heat exchanger, a method thereof and a fission reactor system.

  When operating a nuclear fission reactor, it is known that neutrons of known energy are absorbed by nuclides having a high atomic weight. The resulting compound nucleus divides into splitting products, including two lower atomic splitting fragments and decay products. Nuclides known to perform such splitting with neutrons of all energies include uranium-233, uranium-235 and plutonium-239, which are splitting nuclides. For example, thermal neutrons having a kinetic energy of 0.0253 eV (electron volts) can be used for fission uranium-235 nuclei. Thorium-232 and uranium-238 are fertile nuclides and do not induce induced fission. An exception is fast neutrons with a kinetic energy of at least 1 MeV (million electron volts). The total kinetic energy released from each splitting phenomenon is approximately 200 MeV. Kinetic energy is converted to heat.

  In a nuclear reactor, the fissile and / or fertile feedstock is typically stored in a plurality of closely together packed fuel assemblies that define a nuclear reactor core. The fissile and / or fertile feed may be a mixture of plutonium and uranium oxides in the form of fuel pellets stored in fuel rods separated by spacers. Or it can be a wire spirally wound around each fuel rod.

  Furthermore, in commercial nuclear reactors, the fission heat is converted to electricity. In doing so, the first coolant of the reactor is pumped through the reactor fuel assembly defining the reactor core and heated by the splitting process. In some reactor designs, the heated first coolant is conveyed to a steam generator. Here, the heated first coolant transfers its heat to a second coolant (i.e., water) disposed in the steam generator. The first coolant then returns to the reactor core. A portion of the water that has received the heat of the first coolant evaporates into steam, which moves to the turbine generator to generate electricity. Steam passing through the turbine generator moves to a compressor that compresses the steam into water and then returns to the steam generator.

  A type of fission reactor that can safely generate electricity is a pool type liquid sodium fast breeder reactor. At that time, uranium-238 is used as a fertile raw material. Uranium-238 absorbs neutrons and is converted to splittable plutonium-239 by beta decay. Plutonium-239, in turn, absorbs neutrons and begins to split to generate heat. In fast breeder reactors, controlled raw materials such as water are not required as coolants. Rather, in such a pooled liquid sodium fast breeder reactor, sodium is the chosen coolant. This is because sodium does not turn neutrons into thermal neutrons. In addition, due to the heat transfer characteristics of sodium, the reactor core can be operated at a higher power density, thereby reducing the size of the reactor. In addition, sodium melts at approximately 100 ° C. (approximately 212 ° F.) and boils at approximately 900 ° C. (approximately 1650 ° F.). Therefore, since sodium can be used at a high temperature without boiling, high temperature and high pressure steam can be generated. In the future, this will increase the thermal efficiency of the power plant.

  However, the sodium coolant circulating in the reactor core becomes radioactive due to absorption of neutrons. This radioactivity allows reactor designers to use an intermediate heat exchange loop between the first sodium coolant loop and the steam generation loop. This reduces the risk of radioactive contamination of the turbine generator. In addition, steam generator pipe leakage may occur. When a leak occurs in a pipe that carries sodium through the steam generator, the hot radioactive sodium that passes through the steam generator actively reacts chemically with the water and steam in the steam generator. This causes radioactive contamination of water and steam in the steam generator, resulting in radioactive contamination of the surrounding biosphere. For these reasons, reactor designers can place an intermediate heat exchanger between the reactor core and steam generator to break the direct contact between sodium in the reactor core and the steam generator or turbine generator. Introduce and use.

  Therefore, in the pool type liquid sodium fast breeder reactor described above, an intermediate heat exchanger forms a boundary between radioactive primary sodium and non-radioactive secondary sodium in the steam generator. In other words, an intermediate heat exchanger is placed with the reactor core in a pool of liquid sodium and is typically used to remove heat from the fast breeder core and carry it to an external steam generator .

  An attempt to adequately remove heat from a fast breeder core using an intermediate heat exchanger was published on October 13, 1981, inventor Peter Humphreys et al., US Pat. No. 4,294,658, entitled “Reactor”. Which is arranged in the basic region of the module that drives the first coolant through the heat exchanger, the intermediate heat exchanger of the tube in the shell and the intermediate heat exchange with the electromagnetic flow coupler A vessel module is disclosed. This patent describes a serious heat shock that occurs in an intermediate heat exchanger, for example, when a coolant flow failure occurs in the associated second coolant circuit, caused by a failure of the second coolant pump. . According to this patent, the object of the invention occurs in an intermediate heat exchanger of a reactor that is cooled with pool-type liquid metal in an emergency such as when the flow flow of the second coolant circuit fails. To reduce heat shock.

  Another attempt to adequately remove heat from a fast breeder core using an intermediate heat exchanger was issued on April 13, 1982, inventor Michael G. Sowers et al., US Pat. No. 4,324,617, title of invention. There are “intermediate heat exchangers and methods for liquid metal cooled reactors”. This patent discloses a heat exchanger for use in a multi-pool, liquid metal cooled nuclear reactor. This patent discloses the provision of differential thermal expansion between the structural components of the heat exchanger. According to this patent, the heat exchanger shell is brought to a temperature substantially higher than the temperature of the heat exchanger tube by pulling the tube during operation by heat transfer with the hot pool and by heating the shell. To provide a differential heat expansion in the heat exchanger.

  Although the techniques described above may disclose apparatus and methods that adequately serve their intended purpose, any of the techniques described above may include heat exchangers, methods and fission reactors described and claimed herein. The system is not disclosed.

[Summary of the Invention]
The present disclosure provides the following:
A heat exchanger that can be used in a pooled fission reactor capable of generating heat and can be placed in a pool fluid present in the pooled fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
The heat exchanger includes a heat exchanger body and heat removal means formed integrally with the heat exchanger body.

The present disclosure provides the following:
A heat exchanger that can be used in a pooled fission reactor capable of generating heat and can be placed in a pool fluid present in the pooled fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
The heat exchanger includes a heat exchanger body having a surface formed therein and defining a portion of the plenum volume.

The present disclosure provides the following:
A heat exchanger that can be used in a pooled fission reactor capable of generating heat and can be placed in a pool fluid present in the pooled fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
The heat exchanger
A heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, the heat exchanger having a surface formed therein and defining a portion of the plenum volume The body,
A heat transfer member coupled to the heat exchanger body and defining a flow path therethrough.

The present disclosure provides the following:
A heat exchanger that can be used in a pooled fission reactor capable of generating heat and can be placed in a pool fluid present in the pooled fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
The heat exchanger
A heat exchanger body having a surface formed therein and defining a portion of the plenum volume shaped for a predetermined flow rate of heat transfer fluid entering the portion of the plenum volume;
A plurality of adjacent heat transfer members connected to the heat exchanger body, the plurality of adjacent heat transfer members being spaced apart by a predetermined distance that defines a plurality of flow paths between opposing ones. And a plurality of adjacent heat transfer members that distribute the flow rate of the heat transfer fluid through the plurality of flow paths.

The present disclosure provides the following:
A system used for a pooled nuclear fission reactor,
A fission reactor core capable of generating heat,
A heat exchanger main body corresponding to the nuclear fission nuclear core, the heat exchanger main body being capable of being arranged in the pool fluid in the vicinity of the inner periphery of the pool wall for confining the pool fluid;
It includes heat removal means for transferring heat to the fission reactor core and corresponding to the heat exchanger body.

The present disclosure provides the following:
A system used for a pooled nuclear fission reactor,
A container defining a pool wall having an inner periphery, wherein the pool wall is configured to confine pool fluid therein;
A fission reactor core that can be placed in a vessel and can generate heat,
Heat transfer transfer with the fission reactor core can be placed in the pool fluid near the inner periphery of the pool wall, formed there and shaped to achieve a predetermined flow rate of the heat transfer fluid entering the plenum volume A heat exchanger body having a surface defining a portion of the measured plenum volume;
It includes heat removal means for transferring heat to the fission reactor core and corresponding to the heat exchanger body.

The present disclosure provides the following:
A system used for a pooled nuclear fission reactor,
A pressure vessel defining a pool wall having an inner periphery, wherein the pool wall is configured to confine pool fluid therein;
A fission reactor core placed in a pressure vessel and capable of generating heat,
Heat transfer with the fission reactor core, can be placed in the pool fluid, near the inner periphery of the pool wall, formed there and molded there for a given flow rate of heat transfer fluid entering the plenum volume A heat exchanger body having a surface defining a portion of the measured plenum volume;
A plurality of adjacent heat transfer members connected to the heat exchanger body, the plurality of adjacent heat transfer members being spaced apart by a predetermined distance that defines a plurality of flow paths between opposing ones. And a plurality of adjacent heat transfer members that distribute the flow rate of the heat transfer fluid through the plurality of flow paths.

The present disclosure provides the following:
Used for pool-type fission reactors capable of generating heat,
A method of manufacturing a heat exchanger that can be placed in a pool fluid existing in a pool-type fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
Receive the heat exchanger body,
A heat removal means is coupled to the heat exchanger body.

The present disclosure provides the following:
Used for pool fission reactors,
A method of manufacturing a heat exchanger that can be placed in a pool fluid existing in a pool-type fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
A heat exchanger body having a surface formed thereon and defining a portion of the plenum volume is received.

The present disclosure provides the following:
Used for pool-type fission reactors capable of generating heat,
A method of manufacturing a heat exchanger that can be placed in a pool fluid existing in a pool-type fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
A heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, the heat exchanger having a surface formed therein and defining a portion of the plenum volume Receive the body,
A heat transfer member defining a flow path therethrough is coupled to the heat exchanger body.

The present disclosure provides the following:
Used for pool-type fission reactors capable of generating heat,
A method of manufacturing a heat exchanger that can be placed in a pool fluid existing in a pool-type fission reactor,
The heat exchanger can be placed near the inner periphery of the pool wall that confines the pool fluid,
Receiving a heat exchanger body formed thereon and having a surface defining a plenum volume shaped for a predetermined flow rate of heat transfer fluid entering the plenum volume;
A plurality of adjacent heat transfer members are connected to the heat exchanger body, and a plurality of adjacent heat transfer members are spaced apart by a predetermined distance to define a plurality of flow paths between opposing ones of the heat transfer members, Distributes the flow rate of the heat transfer fluid through the plurality of channels.

  A feature of the present disclosure is to provide a heat exchanger body that defines a chamber formed therein for a constant flow rate of heat transfer fluid through the chamber.

  A further feature of the present disclosure is a plurality of adjacent heat transfer members connected to the heat exchanger body, wherein a predetermined distance is defined to define a plurality of flow paths between each of the plurality of adjacent heat transfer members. It is to provide a plurality of adjacent heat transfer members that are spaced apart and evenly distribute the flow of heat transfer fluid through the plurality of flow paths.

  In addition to the foregoing, various other method and / or apparatus features are disclosed in the teachings of the present disclosure (eg, the claims and / or detailed description) and / or drawings.

  The foregoing is a summary and may thus include simplification, generalization, inclusion and / or omission of details. Accordingly, those skilled in the art will appreciate that this summary is for illustration only and does not imply any limitation. In addition to the descriptions, embodiments, and features described above, further features and embodiments will become apparent by reference to the drawings and the following detailed description.

[Brief description of the drawings]
While the specification concludes with claims that particularly claim the subject matter of the present disclosure, the disclosure will be better understood from the following detailed description when taken in conjunction with the accompanying drawings. Further, the use of the same numbers in different drawings typically refers to similar or identical members.

  FIG. 1 is a schematic diagram of a fission reactor system.

  FIG. 2 is a horizontal sectional view of a hexagonal fission reactor core including a plurality of fission reactor modules and a breeder reactor module.

  FIG. 3 is a horizontal cross-sectional view of one of a plurality of fission reactor modules and a plurality of control rods therein.

  FIG. 4 is an isometric view of the nuclear fuel rod partially removed for clarity.

  FIG. 5 is a horizontal cross-sectional view of a parallelepiped fission reactor core including a plurality of fission reactor modules and a breeder reactor module.

  FIG. 6 is a vertical cross-sectional view of three exemplary fission reactor modules, partially removed for clarity.

  FIG. 7 is an isometric view of the heat exchanger.

  FIG. 8 is an isometric view of the cross section of the heat exchanger, shown in part by the apparent lines.

  FIG. 8A is an isometric view of a cross section of the heat exchanger showing the guide structure.

  FIG. 9 is a vertical cross-sectional view of the heat exchanger showing the cross flow of the first heat transfer fluid and the second heat transfer fluid.

  FIG. 9A is a vertical cross-sectional view of the heat exchanger showing the backflow of the first heat transfer fluid and the second heat transfer fluid.

  9B is an exploded isometric view of the heat exchanger shown in FIG. 9A showing the backflow of the first and second heat transfer fluids, partially removed for clarity.

  FIG. 9C is a vertical cross-sectional view of a heat exchanger showing a parallel flow of a first heat transfer fluid and a second heat transfer fluid.

  FIG. 9D is an exploded isometric view of the heat exchanger shown in FIG. 9C, showing a parallel flow of the first heat transfer fluid and the second heat transfer fluid, partially removed for clarity.

  FIG. 10 is an isometric view of the flow rate having a plurality of vanes on its outer surface.

  FIG. 11 is an isometric view of the flow rate having a plurality of nodes on its outer surface.

  FIG. 12 is an isometric view of the flow rate having a plurality of vanes on its inner surface.

  FIG. 13 is an isometric view of the flow rate defining a flow path through it and grooves disposed along the flow path.

  FIG. 13A is an isometric view of the flow rate having edge-shaped vanes on its outer surface.

  FIG. 13B is an isometric view of the flow rate where the density increases towards the outer surface.

  FIG. 14 is a schematic view of a plurality of heat exchangers arranged in the pressure vessel.

  15 is a view taken along section line 15-15 in FIG.

  FIG. 16 is a horizontal cross-sectional view of a pressure vessel belonging to a nuclear fission reactor system showing a plurality of adjacent heat exchangers disposed in the pressure vessel.

  FIGS. 17 to 47 are flowcharts for explaining a method of assembling a heat exchanger used for a fission reactor.

Detailed Embodiment of the Invention
In the following detailed description, reference is also made to the accompanying drawings, which form a part hereof. In the drawings, similar member numbers typically identify similar compositions, unless context dictates otherwise. The embodiments, drawings and claims set forth in the detailed description are not intended to be limiting. Other embodiments may be used or other changes may be made without departing from the spirit or scope of the subject matter listed.

  In addition, this application uses formal outline headings for clarity of display. However, throughout this application, summary headings are for display purposes, and other types of subject matter may be discussed (eg, device / structure is described under processing / operations heading and / or processing / It will be understood that operations are discussed under the processing / operation heading and / or a single topic description may span two or more topic headings). From here on, the use of formal summary headings is not intended to be limiting.

  Furthermore, the subject matter described herein sometimes refers to different components that are contained within or connected to other different components. It will be appreciated that such a structure shown is merely an example, and that many other structures that actually accomplish the same function may be implemented. In a conceptual sense, any composition of a composition that accomplishes the same function is effectively “associated” so that the desired function is achieved. From here, any two components that are combined here to achieve a particular function are “related” to each other so that the desired function is achieved regardless of structure or intermediate components. Similarly, any two well-related components can also be “operably connected” or “operably coupled” to each other to achieve the desired function. Any two components that are well related can then be “operably coupleable” to each other to achieve the desired function. Examples of operably coupleable are not particularly limited, but may be physically paired and / or physically interacting components and / or wirelessly interactable and / or wirelessly interacting components and Components that interact and / or logically interact.

  In some examples, one or more components may be “configured” “configurable” “operable / operating” “applied / applicable” “enabled” “matched / matched”, etc. It can be expressed as. One skilled in the art will understand that unless otherwise required, “configured” generally includes an active state composition and / or an inactive state composition and / or a stable state component.

  Therefore, referring to FIG. 1, as a non-limiting example only, a pooled fast neutron fission reactor and system is shown generally as 10. As described more fully hereinafter, fission reactor system 10 is a “traveling wave” fission reactor system. The fission reactor system 10 generates power and is transmitted to power consumers through a plurality of transmission lines (not shown). Alternatively, the fission reactor system 10 can be used to perform tests to investigate the effect of temperature on the reactor material.

With reference to FIGS. 1, 2, and 3, the fission reactor system 10 includes a fission reactor core, generally indicated at 20, which includes a plurality of fission fuel assemblies or fission modules 30 as shown herein. The fission reactor core 20 is sealed and stored inside the reactor core enclosure 40. As a non-limiting example, each fission module 30 may form a hexagonal cross-sectional structure as shown, and therefore compared to other shapes of fission modules 30 such as cylindrical or spherical. More fission modules 30 may be packed close together inside the fission reactor core 20. Each fission module 30 includes a plurality of fuel rods 50 that generate heat by the fission chain reaction process described above. If desired, a plurality of fuel rods 50 may be used when the fission module 30 is placed in the fission reactor core 20 to add structural rigidity to the fission module 30 and to isolate the fission modules 30 from each other. May be surrounded by a fuel rod container 60. Isolating the fission modules 30 from each other is to avoid cross coolant flow crossing between the fuel rods 50. Avoiding cross-flow of crossing coolant is to prevent cross-vibration of the fuel rods 50. Such transverse vibration increases the risk of damage to the fuel rod 50. Also, isolating the fission modules 30 from each other is that the coolant flow based on the individual module-to-module basis can be controlled. Controlling the coolant flow to the individual fission modules 30 is to effectively manage the coolant flow within the fission reactor core 20. This is done, for example, by directing coolant flow in the fission reactor core 20 substantially along an indefinite temperature distribution. In other words, more coolant is directed to the hot fission module 30 to provide a substantially indefinite temperature distribution in the fission reactor core 20. The coolant has an average nominal volume flow of approximately 5.5 m ³ / sec (ie, approximately 194 cubic feet ³ / sec), and for an experimental sodium cooled reactor in normal operation is approximately 2.3 m. An average nominal speed of / second (ie approximately 7.55 feet / second). The fuel rods 50 are adjacent to each other and define a fuel rod coolant flow path 80 therebetween (see FIG. 6), allowing the coolant to flow along the exterior of the fuel rods 50. The container 60 may include means (not shown) for supporting the fuel rods 50 and trying them together. Therefore, the fuel rods 50 are bundled together in the container 60 to form the hexagonal fission module 30 described above. Although the fuel rods 50 are adjacent to each other, the fuel rods 50 are nevertheless spaced by wire wraps (see FIG. 6) that spirally surround and extend along the length of each tortuous fuel rod 50. An open relationship is maintained. This is known to those skilled in the art of nuclear power reactor design.

  Referring to FIG. 3, a plurality of spaced apart, longitudinally extending, longitudinally movable control rods 95 (only some of which are shown) are connected to a control rod guide tube or sheath (see FIG. (Not shown), respectively. The control rods 95 are disposed symmetrically within the selected fission module 30 and extend the length of a predetermined number of fission modules 30. The control rod 95 is shown as being disposed in a predetermined number of hexagonal fission modules 30 and controls the fission reaction occurring in the fission module 30. In other words, the control rod 95 includes a suitable neutron absorber material having a neutron absorption intersection that is as high as acceptable. In this regard, the absorber material is essentially a metal selected from the group consisting of lithium, silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, erbium, europium, and mixtures thereof or It may be a quasi metal. Alternatively, the absorber material is selected from the group consisting essentially of silver-indium-cadmium, boron carbide, zirconium boride, titanium boride, hafnium boride, gadolinium titanate, dysprosium titanate, and mixtures thereof. Or a compound or alloy. The control rod 95 provides controllable negative reactivity to the fission reactor core 20. Therefore, the control rod 95 provides a reactivity management capability for the fission reactor core 20. In other words, the control rod 95 can control the neutron flow profile of the fission reactor core 20 and therefore affects the temperature inside the fission reactor core 20.

  With particular reference to FIGS. 2, 3, and 4, each fuel rod 59 has a plurality of nuclear fuel pellets 100 stacked end to end there, and the nuclear fuel pellet 100 is a fuel rod exterior material. Sealed and surrounded by material 110. The nuclear fuel pellet 100 includes the above-described fission nuclides, such as uranium-235, uranium-233, or uranium-239. Alternatively, the nuclear fuel pellet 100 may include fertile nuclides, such as thorium-232 and / or uranium-238 mutated by neutron capture during the fission process into the fission nuclides just described. Such fertile nuclide material may be stored in a breeder reactor rod disposed in a specifically designated breeder reactor fuel module 115. Such a breeder reactor module 115 may be arranged as a “breeder blanket” around the inner periphery of the fission reactor core 20 for the breeder reactor fuel as is known to fast neutron breeder designers. As yet another example, nuclear fuel pellet 100 may include a predetermined mixture of fission nuclides and fertile nuclides.

Referring to FIG. 4, by way of example and without limitation, nuclear fuel pellet 100 is essentially also referred to as uranium monoxide (UO), uranium dioxide (UO ₂ ), thorium dioxide (ThO ₂ ) (thorium oxide). ), Uranium trioxide (UO ₃ ), uranium oxide-plutonium oxide (UO—PuO), uranium trioxide (U ₃ O ₈ ), and mixtures thereof may be made. . Alternatively, the nuclear fuel pellet 100 may comprise uranium substantially or not alloyed with other metals such as but not limited to zirconium or thorium metals. Alternatively, the nuclear fuel pellet 100 may comprise substantially uranium carbide (UC _x ) or thorium carbide (ThC _x ). For example, nuclear fuel pellets 100 are essentially uranium monocarbide (UC), uranium dicarbide (UC ₂ ), uranium sesquicarbide (U ₂ C ₃ ), thorium carbide (ThC ₂ ), thorium carbide (ThC) and the like. May be made from carbides selected from the group consisting of: As another non-limiting example, the nuclear fuel pellet 100 is essentially composed of uranium nitride (U ₃ N ₂ ), uranium nitride-zirconium nitride (U ₃ N ₂ Zr ₃ N ₄ ), uranium-plutonium nitride ((U— It may be made from a nitride selected from the group consisting of Pu) N), thorium nitride (ThN) and mixtures thereof. The fuel rod cladding material 110 hermetically surrounds the load of nuclear fuel pellets 100 and includes a preferred zirconium alloy, such as ZIRKOLOY ™ (a trademark of Westinghouse Electric Corporation), which is resistant to corrosion and crushing. It is known that there is. The armor material 110 may similarly be made from other materials, such as ferritic martensitic steel.

  With reference to FIG. 1, a fission reactor core 20 may be placed inside a basement or reaction pressure vessel to prevent leakage of radioactive material, gas or liquid from the fission reactor core 20 into the surrounding biosphere. For reasons described below, the pressure vessel 120 has an inner wall surface 122 and is substantially filled with a fluid such as liquid sodium or a pool of coolant 125 to the extent that the fission core 20 is immersed in the pool of coolant. ing. The pressure vessel 120 may be steel, concrete, or other material having a preferred size and thickness to reduce the risk of such radioactive leakage and to support the required pressure load. In addition, a containment vessel (not shown) that seals around the fission reactor system 10 for better assurance to prevent leakage of radioactive particles, gases or liquids from the fission reactor core 20 to the surrounding biosphere. May be provided.

  Referring to FIG. 1, a first loop coolant pipe 130 provides a fission reactor core 20 such that a suitable coolant flows through the fission reactor core 20 along arrows 135 to cool the fission reactor core 20. May be combined. The first loop coolant pipe 130 may be made from a suitable material such as stainless steel. If desired, the first loop coolant pipe 130 may be not only a ferrous alloy, but also a non-ferrous alloy, a zirconium alloy or other suitable structural material or composite. The coolant carried by the first loop coolant pipe 130 may be essentially a liquid metal selected from the group consisting 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). Or, in the embodiment discussed herein, the coolant is a liquid metal (Na) metal or a sodium metal mixture such as sodium-potassium (Na-K). Depending on the particular reactor core design and operating history, the normal operating temperature of a sodium cooled reactor core may be relatively high. For example, for a 500 to 1,500 MWe sodium cooled reactor using a mixed uranium-plutonium oxide fuel, the external temperature of the reactor core during normal operation is approximately 510 ° Celsius (ie, 950 ° Faren). Height) to approximately 550 ° Celsius (ie, 1,020 ° Faren height). On the other hand, during LOCA (Coolant Loss Accident) or LOFTA (Temporary Flow Loss Accident), the peak fuel cladding temperature is approximately 600 ° Celsius (ie 1,110 Faren Height) or May reach higher temperatures. Further, decay heat buildup during post-LOCA or post-LOFT scenarios and during reactor operation shutdown may or may not have unacceptable heat buildup. Therefore, in some cases, it is preferable to remove heat from the fission reactor core 20 during both normal operation and post-accident scenarios.

  With continued reference to FIG. 1, the heat-generating coolant produced by the fission reactor core 20 is an intermediate that is also immersed in the coolant pool 125 along the coolant flow or along the flow path 140. Flow to the correct heat exchanger 150. The intermediate heat exchanger 150 may be made from any convenient material that is resistant to heat and the corrosive action of the sodium coolant pool 125, such as suitable stainless steel. As described in more detail below, the coolant flowing along the coolant flow path 140 flows through the intermediate heat exchanger 150. Then it continues through the first loop coolant pipe 130. It will be appreciated that the coolant leaving the intermediate heat exchanger 150 is cooled by the heat transfer that occurs in the intermediate heat exchanger 150, as described in more detail below. The first pump 170 may be an electromechanical pump and is coupled to the first loop pipe 130 to transfer fluid to and from the reactor coolant carried by the first loop coolant pipe 130. Reactor coolant through one loop pipe 130 is pumped and routed through reactor core 20 and along coolant flow path 140 to intermediate heat exchanger 150.

  Referring again to FIG. 1, a second loop pipe 180 is provided to remove heat from the intermediate heat exchanger 150. Second loop pipe 180 includes a second “hot” leg pipe segment 190 and a second “cold” leg pipe segment 200. The second hot pipe segment 190 and the second cold pipe segment 200 are integrally connected to an intermediate heat exchanger 150. The second loop pipe 180 includes a second hot pipe segment 190 and a second cold pipe segment 200 and is essentially a liquid metal selected from the group consisting of sodium, potassium, lithium, lead and mixtures thereof. Including fluids. On the other hand, the fluid may be a metal alloy such as lead-bismuth (Pb-Bi). Alternatively, in the embodiments discussed herein, the fluid may be a liquid sodium (Na) metal or a sodium metal mixture such as sodium-potassium (Na-K), as appropriate. The second hot pipe segment 190 extends from the intermediate heat exchanger 150 to a steam generator and superheater combination 210 (hereinafter “steam generator 210”) for reasons that will be discussed shortly. . In this regard, the coolant passing through the second loop pipe 180 and the outlet steam generator 210 is transferred to the steam generator 210 by the heat transfer generated inside the steam generator 210 after passing through the steam generator 210. Lower temperature and enthalpy than before entering. After passing through the steam generator 210, the coolant is pumped, such as by the second pump 220. This pump may be an electromechanical pump and is along a “cold” leg pipe segment 200 and extends to an intermediate heat exchanger 150 to provide the heat transfer described above. The manner in which the steam generator 210 generates steam will generally be described shortly thereafter.

  Referring again to FIG. 1, the steam generator 210 is a body of water 230 having a predetermined temperature and pressure. The fluid passing through the second hot leg pipe segment 190 transfers heat by heat conduction with the body of water 230, which is cooler than the fluid passing through the second hot leg pipe segment 190. The fluid passing through the second hot leg pipe segment 190 transfers heat to the body of water 230, and a portion of the body of water 230 is vaporized into steam 240 by a predetermined temperature and pressure inside the steam generator 210. . Steam 240 then travels through steam line 250. The vapor line 250 communicates vapor with the vapor 240 at one end and communicates liquid with the main body of the water 230 at the other end. A steam turbine 250 is coupled to the steam line 250, and the turbine 260 rotates as the steam 240 passes therethrough. When the turbine 260 rotates, the generator 270 coupled to the turbine 260 generates power by using a rotatable turbine shaft 280 or the like. Further, a compressor 290 is coupled to the steam line 250 and receives steam passing through the turbine 260. The compressor 290 compresses the vapor to liquid water and sends the waste heat to a heat sink such as the cooling tower 300 corresponding to the compressor 290. Liquid water compressed by the compressor 290 is pumped from the compressor 290 along the steam line 250 to the steam generator 210 using a third pump 310. The third pump 310 may be an electromechanical pump inserted between the compressor 290 and the steam generator 210.

  As best shown in FIG. 5, the fission module 30 may be configured to define a parallelepiped-shaped fission reactor core configuration, generally as in 222 rather than the hexagonal configuration described above. It is assumed. In this regard, the reactor core enclosure 40 of the fission reactor core 222 defines a first end 330 and a second end 340 for reasons described below.

  Referring again to FIG. 5, regardless of the configuration chosen as the fission reactor core, the fission reactor core 20 or 222 may be configured as a traveling wave fission reactor core. In this regard, the relatively small and movable fission igniter 350 may include isotope enrichment of materials capable of fission, such as but not limited to U-233, U-235, or Pu-239, and Appropriately arranged at 222. As a non-limiting example, the igniter 350 is disposed near the first end 330 opposite the second end 340 of the reactor core 340. Neutrons are emitted by the igniter 350. Neutrons emitted by the igniter 350 are captured by the fissionable and / or fertile material inside the fission module 30 and initiate a fission chain reaction. If desired, the igniter 350 may be removed once the split chain reaction is auto-continuous.

  With continued reference to FIG. 5, the igniter 350 initiates a three-dimensional progressive deflagration wave or “burn wave” 360. When neutrons are emitted and “ignited” by the igniter 350, the burn wave 360 moves outward from the igniter 350 near the first end 330 and toward the second end 340 of the reactor core 222. Thereby, a traveling or propagating burn wave 360 is formed. In other words, as the burn wave 360 propagates through the reactor core 222, each fission module 30 can accept at least a portion of the traveling burn wave 360. The speed of the traveling burn wave 360 is constant or non-constant. Therefore, the propagation speed of the burn wave 360 can be controlled. For example, the longitudinal movement of the aforementioned control rod 95 (see FIG. 3) in a predetermined or programmed manner can reduce the neutron reactivity of the fuel rod 50 disposed in the fission module 30. In this way, the neutron reactivity of the fuel rod 50 that is currently burned at the location of the burn wave 360 is reduced compared to the neutron reactivity of the “non-burning” fuel rod 50 before the burn wave 360. . As a result, the propagation direction of the burn wave indicated by the directivity arrow 365 is given. By controlling the reactivity in this manner, the propagation speed of the burn wave 360 is maximized in accordance with the operational limitations of the reactor core 220. For example, maximizing the propagation speed of the burn wave 360, in part, controls the combustion above the minimum required for propagation and a set of maximums due to the neutron fluence limit of the structural material of the reactor core. Is to provide a means.

  The basic principle of such a traveling wave fission reactor is described in pending US patent application 11 / 605,943 (filed Nov. 28, 2006, inventor Roderick A. Hyde, et al., Entitled "Automated Nuclear Power Reactor"). For Long-Term Operation ”), which is assigned to the assignee of the present application, the entire disclosure of which is hereby incorporated by reference.

  Referring to FIG. 6, an upright, adjacent hexagonal fission module 30 is shown. Although only three adjacent fission modules 30 are shown, it will be appreciated that there are more fission modules 30 in the reactor core 20. Each fission module 30 is mounted on a lower support plate 370 of the nuclear core that extends in the horizontal direction. The lower support plate 370 of the reactor core extends moderately beyond the bottom end of all fission modules 30. The lower support plate 370 of the reactor core has a counter hole 380 therethrough for reasons described below. Counter hole 380 has an open end 390 that allows the flow of coolant into it. A nuclear reactor upper support plate 400 that covers all fission modules 30 extends horizontally beyond the top end or discharge of the fission module 30 and is movably connected to the fission module 30. The upper support plate 400 of the reactor core also defines a plurality of flow channels 410 that allow coolant flow therethrough. A first loop pipe 130 and a first pump 170 (see FIG. 1) carry reactor coolant to the fission module 30 along a coolant flow path or fluid vapor as indicated by a directional arrow 140. The first coolant then continues along the flow path 140 and passes through the open end 390 formed in the lower support plate 370.

  As described above, regardless of the configuration selected as the fission reactor core 20, it is important to remove the heat generated by the fission reactor core 20 and the fission module 30 there. Proper heat removal is important for several reasons. For example, if the peak temperature exceeds the material limit, the structural material of the reactor core will be thermally damaged. Such peak temperatures cause an undesired decrease in the operating life of the structure according to the peak temperature by changing the mechanical properties of the structure, particularly those related to thermal creep. Also, the power density of the reactor is limited by the ability of the core structural material to withstand high peak temperatures without damage. Further, alternatively, the fission reactor system 10 can be used to perform tests such as tests that determine the effect of temperature on the reactor material. Controlling the temperature of the reactor core by properly removing heat from the reactor core is important for successful such testing.

  In addition, it is desirable to achieve a constant flow rate of the heat transfer fluid through the intermediate heat exchanger 150. Such a constant flow rate can avoid uneven flow rates of coolant to the nuclear reactor core and thereby core reactive perturbations. Furthermore, it is desirable to have a constant distribution of coolant flow through the heat exchanger to avoid preferential flow of coolant through the heat exchanger. By avoiding preferential flow of coolant, the occurrence of local “hot spots” in the heat exchanger can be mitigated. Such local temperature “hot spots” reduce the operating life of the heat exchanger. Further, the constant flow rate enhances heat exchange uniformly across the heat transfer surface of the heat exchanger and enhances heat exchange for a predetermined heat exchange region. The structure and operation of the intermediate heat exchanger 150 addresses this concern.

  The structure of the intermediate heat exchanger 150 will be described.

  Referring to FIGS. 1, 7, 8, 8 </ b> A and 9, an intermediate heat exchanger 150 includes a heat exchanger body 420 attached to the inner wall surface 122 of the pressure vessel 120. A typical heat exchanger 150 is supported inside the pressure vessel 120. Alternatively, the inner wall surface 122 forms the rear wall of the intermediate heat exchanger 150 with the confinement pool 125. The heat exchanger body 420 includes an upright, generally (cross-sectional) L-shaped rear portion 425. The rear 425 defines therein a first fluid outlet plenum volume or outlet plenum chamber 430. Accordingly, the first fluid outlet plenum chamber 430 is part of the heat exchanger body 420. The first fluid outlet plenum chamber 430 is shaped to provide a constant flow rate of the first heat transfer fluid (ie, primary heat transfer fluid) through the first fluid outlet plenum chamber 430, as described in more detail below. Has been. A first fluid outlet port that opens into the first loop coolant pipe 130 is formed inside the first fluid outlet plenum chamber 430 through the rear 425 of the heat exchanger body 420. Connected to the rear 425 is a bottom 440 of the heat exchanger body 420 that defines a bottom plenum 450 for hot second sodium. The bottom plenum 450 has a bottom plenum outlet side or port 455 that forms a box structure having an uppermost surface 460 on which a plurality of upright plate-shaped heat transfer members 470 are welded. Etc. are integrally attached. Each heat transfer member 470 defines a flow path 460 therethrough having an inlet 490 and an outlet 500 at each end of the flow path 460. The inlet 490 communicates fluid to and from the heat transfer fluid flow through the cold leg pipe segment 200. The outlet 500 communicates fluid with the heat transfer fluid at the bottom plenum 450. Further, it will be appreciated that the first fluid is supplied to the heat exchanger body 420 without a groove or manifold. In other words, the first fluid is supplied to the heat exchanger body 420 without a groove or a manifold. It will be appreciated that the pool 125 is also without a manifold. Further, it will be appreciated that the inlet side of the intermediate heat exchanger 150 may be without a manifold and the outlet side of the intermediate heat exchanger 150 may be without a manifold. Thereby, since such a groove | channel and a manifold are unnecessary, the cost which manufactures the capital which manufactures the nuclear reactor 10, and / or the heat exchanger 150 can be reduced.

  With reference to FIGS. 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” for defining a plurality of flow paths 510 between the plurality of adjacent heat transfer members 470. The distance “d” is the distance necessary to achieve a uniform flow distribution between the channels 510. In other words, the heat transfer members 470 are spaced apart by a distance “d” to evenly distribute the flow rate of the first heat transfer fluid through the plurality of channels 510. In order to achieve a uniform distribution of the flow rate of the first heat transfer fluid through the plurality of flow paths, the distance “d” between adjacent heat transfer members 470 may be varied between various reactor cores as required. It may be designed to have various values for the configuration. In this way, certain reactor core configurations change the internal structure that alters or interferes with the free flow of the first heat transfer fluid as it moves toward the heat exchanger 150. It is because it has. To compensate for this effect, the distance “d” may be designed to have various values. In another embodiment, the heat exchanger body 420 may include a guide structure 515 that guides the flow of heat transfer fluid entering the heat exchanger 150. The guide structure 515 moderately bridges the heat transfer member 470 and is connected to the flow path 510, so that the heat transfer fluid is guided to the flow path 510. The heat exchanger body 420 further includes a top portion 520 that is mounted on or connected to the top of the rear portion 425 and the top of the plurality of heat transfer members 470. The top 520 defines a top plenum therein for receiving cooled second sodium flowing along the flow path 532 from the steam generator 210. The cooled second sodium flowing along the flow path 532 and the first heat transfer fluid flowing along the flow path 140 define a cross flow direction. In this cross-flow direction, the flow path 532 is substantially perpendicular (ie, plus or minus 45 degrees) to the flow path 140 in the intermediate heat exchanger 150. The top plenum 530 communicates with the inlet 490 to allow the cooled second sodium to flow through the inlet 490, into the flow path 470, through the outlet 500, and into the bottom plenum 450. .

  Referring to FIGS. 9A and 9B, an alternative embodiment of intermediate heat exchanger 150 is a cold leg pipe segment in which a cooled second heat transfer fluid flows through flow path 532 through segment 200. 200. In this regard, the cooled second heat transfer fluid passes through opening 536a, enters plate 534, and exits through opening 536b formed in plate 534. The second heat transfer fluid continues to flow along the flow path 532 and enters the return pipe segment 538 for returning the second heat transfer fluid to the steam generator 210. The cooled second sodium flowing along the flow path 532 and the first heat transfer fluid flowing along the flow path 140 define a reverse flow direction. In this reverse flow direction, the flow path 532 is parallel to the flow path 140 of the intermediate heat exchanger 150, but in the opposite direction.

  With reference to FIGS. 9C and 9D, an alternate embodiment intermediate heat exchanger 150 includes a cold leg pipe segment 200. A cooled second heat transfer fluid flows through the cold leg pipe segment 200 along the flow path 532. In this regard, the cooled second heat transfer fluid passes through opening 536a, enters plate 534, and exits through opening 536b formed in plate 534. The second heat transfer fluid continues to flow along the flow path 532 and enters the return pipe segment 538 for returning the second heat transfer fluid to the steam generator 210. The cooled second heat transfer fluid flowing along the flow path 532 and the first heat transfer fluid flowing along the flow path 140 define a parallel flow direction. In this parallel flow direction, the flow path 532 is parallel to and in the same direction as the flow path 140 of the intermediate heat exchanger 150.

  With reference to FIGS. 10, 11, 12, and 13, an alternative embodiment of heat transfer member 470 is shown. In this regard, at least one of the plurality of heat transfer members 470 defines an enhanced heat transfer surface 550 that contains a flow of a first heat transfer fluid along the enhanced heat transfer surface 550. A wall 540 is included. In this regard, the wall 540 separates the hot first sodium (ie, the second heat transfer fluid) from the cold second sodium (ie, the second heat transfer fluid). At least one of the plurality of heat transfer members 470 extends at least one integrally connected external vane or external flange extending outwardly from the wall 540 to form a reinforced heat transfer surface 550. 560. The outer flange 560 enhances heat transfer by increasing the surface area for increased heat transfer. Alternatively, at least one of the plurality of heat transfer members 470 includes at least one node 570 that protrudes outward from the wall 540 to form a reinforced heat transfer surface 550. Node 570 enhances heat transfer by increasing the surface area for increased heat transfer. Alternatively, at least one of the plurality of heat transfer members 470 includes at least one integrally connected internal vane or internal flange 580 that extends inwardly from the wall 540 for enhanced heat transfer. Including. Inner flange 580 enhances heat transfer by increasing the surface area for increased heat transfer. In yet another example, at least one of the plurality of heat transfer members 470 extends at least one along a flow path 490 for receiving a flow of cooled heat transfer fluid through a conduit 590. Two grooves 590 are included.

  FIGS. 13A and 13B show a further embodiment that includes a heat transfer surface 550. In this regard, the outer flange 560 may increase the area of the heat transfer surface because the flange 560 extends from the front portion 592 of the wall 540 to the rear portion 594 of the wall 540. As will be appreciated by those skilled in thermodynamics, more of the heat transfer occurs near the front 592 of the wall 540 than near the back of the wall 540. This is because the first heat transfer fluid flows from the front portion 592 of the wall 540 to the rear portion 594 of the wall 540. Therefore, more heat transfer occurs near the front portion 592 of the wall 540 and reduced heat transfer occurs near the rear portion 594 of the wall 540. In order to compensate for the reduced heat transfer in the vicinity of 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 so that the area of the heat transfer surface of the flange 560 is reduced. To increase. For example, the flange 560 may have a wedge shape with a smaller end near the front portion 592 and a wider end near the rear portion 594. As another alternative, to increase the area of the heat transfer surface from the front portion 592 of the wall 540 to the rear portion 594 of the wall 540, the density of nodes 570 projecting outward from the wall 540 (ie, nodes 570 per unit area). May increase from the front portion 592 to the rear portion 594. This configuration of node 570 compensates for the reduced heat transfer near the back 594 of wall 540.

  14 and 15, an alternative embodiment of the fission reactor system 10 is shown. Here, a plurality of heat exchangers such as the first heat exchanger 600 and the second heat exchanger 610 are provided. Each of the first heat exchanger 600 and the second heat exchanger 610 includes a first cold leg pipe segment 620a and a second cold heat supplying a cooled heat transfer fluid to the heat exchanger 600/610, respectively. Coupled to steam generator 210 by leg pipe segment 620b. Further, each of the first heat exchanger 600 and the second heat exchanger 610 includes a first hot leg pipe segment 630a and a second heat pipe fluid 630a that discharge heated heat transfer fluid from the heat exchanger 600/610, respectively. The hot leg pipe segment 630b is coupled to the steam generator 210. Further, if desired, the first cold leg pipe segment 620a can be provided with a first shut-off valve 640a and the second cold leg pipe segment 620b can be provided with a second shut-off valve 640b for the reasons just described. Also good. Furthermore, for the reasons just described, a third shut-off valve 650a may be provided on the first hot leg pipe segment 630a, and a fourth shut-off valve 650b may be provided on the hot leg pipe segment 630b. In this regard, if desired, the shut-off valves 640a / 650a may be closed to stop the coolant flow to and from the first heat exchanger 600. Thus, the first heat exchanger 600 can be isolated. If desired, the shut-off valves 640b / 650b can also be closed to stop the coolant flow to and from the second heat exchanger 610. Thereby, the second heat exchanger 610 can be isolated. If a leak occurs at the wall 540 of any heat transfer member 470, it may be desirable to isolate either the first heat exchanger 600 or the second heat exchanger 610. In addition, multiple pumps, such as pumps 660a and 660b, may be connected to each of the multiple heat exchangers 600 and 610 to pump the cooled heat transfer fluid from the heat exchangers 600 and 610 to the fission reactor core 20, respectively. Is bound to.

  Referring to FIG. 16, a plurality of heat exchangers 670a, 670b, 670c, 670d, 670e, 670f, and 670g are arranged side by side or surround the inner wall surface 122 of the pressure vessel 120 in contact with each other. An embodiment is shown. This embodiment provides another configuration that uses an intermediate heat exchanger 150.

  The operation of the intermediate heat exchanger 150 is further described with reference to FIGS. 1, 6, 8, 8 </ b> A, 9, 10, 11, 12, and 13. In this regard, the heat generated by the fission process by the fuel rod 50 of the nuclear fission reactor core 20 is also referred to as a primary heat transfer fluid, here also referred to as a first heat transfer fluid. When heat is generated, the first pump 170 is operated to draw or draw the first heat transfer fluid from the heat exchanger 150, and then the first heat transfer fluid past the fuel rod 50 is removed from the core. Pump through the flow channel in the upper support plate 400 into the coolant pool. The first pump 170 is continuously operated to draw the first heat transfer fluid through the flow path 510 and into the first fluid outlet plenum chamber 430. As the first heat transfer fluid flows through the channel 510, the first heat transfer fluid is 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 cooler second heat transfer fluid flows from the steam generator 210 along the cold pipe segment 200 along the uppermost plenum 530. Enter the bottom plenum 450 through the inlet 490, through the flow path 480, through the outlet 500. Thereafter, the second heat transfer fluid exits the bottom plenum 450 and is received by the hot leg pipe segment 190 through the outlet port 455 and through the steam generator 210. A second heat transfer fluid that travels along a portion of the hot leg pipe segment 190 and passes through the steam generator 210 transfers that heat to the body of water 230 to produce steam 240. The second pump 220 operates to carry the cooler second fluid from the steam generator 210 to the uppermost plenum 520.

  1, 6, 7, 8, 8 A, 9, 10, 11, 12, and 13, the first heat transfer fluid on the high temperature side passing through the channel 510. Heat is transferred to the second heat transfer fluid on the low temperature side through the flow path 480. This heat transfer is conducted by conduction through the wall 540 of the heat transfer member 470.

  With continued reference to FIGS. 1, 6, 7, 8, 8, 8A, 9, 10, 11, 12, and 13, the first heat transfer fluid passing through the plurality of flow paths 510 is separated. The plurality of adjacent heat transfer members 470 are spaced apart by the predetermined distance “d” as described above. As described above, the first fluid outlet plenum chamber 430 is shaped to provide a constant flow rate of the first heat transfer fluid (ie, primary heat transfer fluid) through the first fluid outlet plenum chamber 430. Yes. In this regard, the upper portion of the first fluid outlet plenum chamber 430 is disposed closer to the inner wall surface 122 and therefore has a smaller volume than the lower portion of the first fluid outlet plenum chamber 430. In other words, the volume of the first fluid outlet plenum chamber 430 is larger on the side closer to the outlet port 435 than on the inlet 490. This shape of the first fluid outlet plenum chamber 430 provides a constant flow rate of the first heat transfer fluid (ie, primary heat transfer fluid) through the first fluid outlet plenum chamber 430.

[Description of method]
A description of the method for embodiments of the fission reactor system and heat exchanger is provided below.

  The method described with reference to FIGS. 17-47 is used in conjunction with a fission reactor capable of generating heat and is provided to assemble a heat exchanger.

  Referring to FIG. 17, the described method 680 used in association with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 690. At block 700, the method includes receiving a heat exchanger body. At block 710, the heat removal means is coupled to the heat exchanger body. The method ends at block 720.

  Referring to FIG. 18, the described method 730 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 740. At block 750, the method includes receiving a heat exchanger body. At block 760, the method includes coupling a heat removal means to the heat exchanger body. At block 770, the method includes coupling a heat removal means configured to achieve a predetermined flow rate of heat transfer fluid entering the heat exchanger body. The method ends at block 780.

  Referring to FIG. 19, the described method 790 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 800. At block 810, the method includes receiving a heat exchanger body. At block 820, the heat removal means is coupled to the heat exchanger body. At block 830, a heat removal means configured to achieve a predetermined flow rate of heat transfer fluid entering the heat exchanger body is coupled. At block 840, heat removal means configured to achieve a substantially constant flow rate of heat transfer fluid entering the heat exchanger body is coupled. The method ends at block 850.

  Referring to FIG. 20, the described method 860 used in association with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 870. At block 880, the method includes receiving a heat exchanger body. At block 890, the heat removal means is coupled to the heat exchanger body. At block 900, a heat removal means having an enhanced heat transfer surface is coupled. The method ends at block 910.

  Referring to FIG. 21, the described method 920 used in association with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 930. At block 940, a heat exchanger body is received. At block 950, the heat removal means is coupled to the heat exchanger body. The method ends at block 970.

  Referring to FIG. 21A, the described method 971 used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 973. At block 975, the method includes receiving a heat exchanger body. At block 977, the heat removal means is coupled to the heat exchanger body. At block 978, a heat exchanger body without a manifold is received. The method ends at block 979.

  Referring to FIG. 22, the described method 980 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 990. At block 1000, the method includes receiving a heat exchanger body having a surface formed therein that defines a portion of the plenum volume. The method ends at block 1010.

  Referring to FIG. 22A, the described method 1011a used in association with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1013a. At block 1015a, the method includes receiving a heat exchanger body having a surface formed therein that defines a portion of the plenum volume. At a block 1017a, a guide structure for guiding pool fluid flow is received. The method ends at block 1019a.

  Referring to FIG. 22B, the described method 1011b used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1013b. At block 1015b, the method includes receiving a heat exchanger body having a surface formed therein and defining a portion of the plenum volume. At block 1017b, a guide structure for guiding the pool fluid flow is received. At block 1018b, a guide structure configured to achieve a substantially constant flow rate of pool fluid is received within at least a portion of the heat exchanger body. The method ends at block 1019b.

  Referring to FIG. 22C, the described method 1011c used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1013c. At block 1015c, the method includes receiving a heat exchanger body having a surface formed therein that defines a portion of the plenum volume. At block 1017c, a heat exchanger body having an inlet guide structure for guiding an inlet flow rate of the pool fluid is received. The method ends at block 1019c.

  Referring to FIG. 22D, the described method 1011d used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1013d. At block 1015d, the method includes receiving a heat exchanger body having a surface formed therein that defines a portion of the plenum volume. At block 1017d, a heat exchanger body having an outlet guide structure for guiding the outlet flow rate of the pool fluid is received. The method ends at block 1019d.

  Referring to FIG. 22E, the described method 1011b used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1013b. At block 1015e, the method includes receiving a heat exchanger body having a surface formed therein that defines a portion of the plenum volume. At block 1017e, a guide structure is received to prevent pool fluid located within at least a portion of the heat exchanger body from contacting the pool wall. The method ends at block 1019e.

  Referring to FIG. 23, the described method 1020 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1030. At block 1040, the method includes receiving a heat exchanger body having a surface formed therein and defining a portion of the plenum volume. At a block 1050, a reactor vessel is defined that defines a portion of the irregularly shaped exit plenum volume. The method ends at block 1060.

  Referring to FIG. 24, the described method 1070 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1080. At block 1090, the method includes receiving a heat exchanger body having a surface formed therein and defining a portion of the plenum volume. At block 1100, a heat exchanger body capable of heat transfer with the fission reactor core is received. The method ends at block 1110.

  Referring to FIG. 25, the described method 1120 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1130. At block 1140, the method includes receiving a heat exchanger body having a surface formed therein that defines a portion of the plenum volume. At block 1150, the method includes receiving a heat exchanger body without a manifold. The method ends at block 1160.

  Referring to FIG. 26, the described method 1170 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1180. At block 1190, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein a portion of the plenum volume is formed therein. Receiving a heat exchanger body having a defining surface. At block 1200, a heat transfer member that defines a flow path therethrough is coupled to the heat exchanger body. The method ends at block 1210.

  Referring to FIG. 27, the described method 1220 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1230. At block 1240, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein a portion of the plenum volume is formed therein. Receiving a heat exchanger body having a defining surface. At a block 1250, a heat transfer member that defines a flow path therethrough is coupled to the heat exchanger body. At block 1260, a heat transfer member configured to achieve a predetermined flow rate of heat transfer fluid entering the heat exchanger body is coupled. The method ends at block 1270.

  Referring to FIG. 28, the described method 1280 used in association with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1290. At block 1300, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein a portion of the plenum volume is formed therein. Receiving a heat exchanger body having a defining surface. At a block 1310, a heat transfer member that defines a flow path therethrough is coupled to the heat exchanger body. At a block 1320, a heat transfer member configured to achieve a predetermined flow rate of heat transfer fluid entering the heat exchanger body is coupled. At a block 1330, a heat transfer member configured to achieve a substantially constant flow rate of heat transfer fluid entering the heat exchanger body is coupled. The method ends at block 1340.

  Referring to FIG. 29, the described method 1350 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1360. At block 1370, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein the heat exchanger body is formed therein to convert a portion of the plenum volume. Receiving a heat exchanger body having a defining surface. At a block 1380, a heat transfer member that defines a flow path therethrough is coupled to the heat exchanger body. At a block 1390, a heat transfer member having a groove extending along the flow path is coupled. The method ends at block 1400.

  Referring to FIG. 30, the described method 1410 used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1420. At block 1430, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein a portion of the plenum volume is formed therein. Receiving a heat exchanger body having a defining surface. At a block 1440, a heat transfer member that defines a flow path therethrough is coupled to the heat exchanger body. At a block 1450, a heat exchanger body capable of heat transfer with the fission reactor core is received. The method ends at block 1460.

  Referring to FIG. 31, the described method 1470 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1480. At block 1490, the method includes a heat exchanger body that defines a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein the heat exchanger body is formed to convert a portion of the plenum volume. Receiving a heat exchanger body having a defining surface. At block 1500, a heat transfer member that defines a flow path therethrough is coupled to the heat exchanger body. At a block 1510, a heat exchanger body capable of transferring heat with the fission reactor core is received. At a block 1515, a heat exchanger body capable of heat transfer with a traveling wave fission reactor core is received. The method ends at block 1520.

  Referring to FIG. 32, the described method 1521 used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1523. At block 1525, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein a portion of the plenum volume is formed therein. Receiving a heat exchanger body having a defining surface. At block 1527, a heat transfer member defining a flow path therethrough is coupled to the heat exchanger body. At a block 1528, a heat exchanger body without a manifold is received. The method ends at block 1529.

  Referring to FIG. 33, the described method 1530 used in association with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1540. At block 1550, the method includes a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, wherein a portion of the plenum volume is formed therein. Receiving a heat exchanger body having a defining surface. At a block 1560, a heat transfer member defining a flow path therethrough is coupled to the heat exchanger body. At a block 1570, a heat transfer member having a wall defining a reinforced heat transfer surface is coupled thereto. The method ends at block 1580.

  Referring to FIG. 34, the described method 1650 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1660. At block 1670, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 1680, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. The method ends at block 1690.

  Referring to FIG. 35, the described method 1700 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1710. At block 1720, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 1730, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 1740, a plurality of adjacent heat transfer members configured to achieve a constant flow rate of heat transfer fluid entering the heat exchanger body are connected. The method ends at block 1750.

  Referring to FIG. 36, the described method 1760 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1770. At block 1780, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 1790, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At a block 1800, a reactor vessel is received that defines a portion of an irregularly shaped exit plenum volume. The method ends at block 1810.

  With reference to FIG. 37, the described method 1820 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1830. At block 1840, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At a block 1850, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At a block 1860, a heat exchanger body capable of transferring heat with the fission reactor core is received. The method ends at block 1870.

  Referring to FIG. 38, the described method 1880 used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1890. At block 1900, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 1910, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At a block 1915, a heat exchanger body capable of transferring heat with the fission reactor core is received. At block 1920, a heat exchanger body capable of heat transfer with the traveling wave fission reactor core is received. The method ends at block 1930.

  Referring to FIG. 39, the described method 1940 used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 1950. At block 1960, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. In block 1970, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 1980, at least two heat transfer fluids having cross flow directions are contained. The method ends at block 1990.

  Referring to FIG. 40, the described method 2000 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2010. At block 2020, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. In block 2030, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 2040, at least two heat transfer fluids having a reverse flow direction are contained. The method ends at block 2050.

  Referring to FIG. 41, the described method 2060 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2070. At block 2080, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 2090, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 2100, at least two heat transfer fluids having parallel flow directions are contained. The method ends at block 2110.

  Referring to FIG. 42, the described method 2120 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2130. At block 2140, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 2150, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 2160, at least one of a plurality of adjacent heat transfer members having a wall defining a reinforced heat transfer surface is coupled for increased heat transfer through the wall. The method ends at block 2170.

  Referring to FIG. 43, the described method 2180 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2190. At block 2200, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. In block 2210, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 2220, at least one of a plurality of adjacent heat transfer members having a wall defining a reinforced heat transfer surface is coupled for increased heat transfer through the wall. At a block 2230, at least one of a plurality of adjacent heat transfer members having flanges extending outwardly from the wall to form a reinforced heat transfer surface is coupled. The method ends at block 2240.

  Referring to FIG. 44, the described method 2000 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2010. At block 2270, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 2280, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 2290, at least one of a plurality of adjacent heat transfer members having a wall defining a reinforced heat transfer surface is coupled for increased heat transfer through the wall. At block 2300, at least one of a plurality of adjacent heat transfer members having flanges extending inwardly from the wall to form a reinforced heat transfer surface is coupled. The method ends at block 2310.

  Referring to FIG. 45, the described method 2320 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2330. At block 2340, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 2350, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At block 2360, at least one of a plurality of adjacent heat transfer members having a wall defining a reinforced heat transfer surface is coupled for increased heat transfer through the wall. At block 2370, at least one of a plurality of adjacent heat transfer members having nodes projecting outwardly from the wall to form an enhanced heat transfer surface is coupled. The method ends at block 2380.

  Referring to FIG. 46, the described method 2390 used in conjunction with a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2400. At block 2410, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 2420, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At a block 2430, a heat transfer member having a groove extending along the flow path is coupled for flow rate of the second heat transfer fluid through the groove. The method ends at block 2440.

  Referring to FIG. 47, the described method 2450 used for a pooled fission reactor capable of generating heat and assembling a heat exchanger begins at block 2460. At block 2470, the method includes receiving a heat exchanger body having a surface formed therein and defining a plenum volume shaped therein for a predetermined flow rate of heat transfer fluid through the plenum volume. At block 2480, a plurality of adjacent heat transfer members are connected to the heat exchanger body and a predetermined distance is defined to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. Distribute the flow rate of the heat transfer fluid through the plurality of channels at intervals. At a block 2490, a heat exchanger body without a manifold is received. The method ends at block 2500.

  Those skilled in the art will appreciate that the elements (eg, operations), devices, objects, and accompanying discussions described herein have been used as examples for purposes of conceptual clarification, and that various configuration modifications are contemplated. You will understand that. Thus, as used herein, the described examples and accompanying discussion are intended to be representative of a more general class. In general, the use of a particular example is intended to be representative of that class, and the absence of a particular element (eg, operation), device, and subject should not be considered limiting.

  Further, those skilled in the art will now be taught elsewhere herein, as the specific example processes and / or apparatus and / or techniques are in the claims appended hereto and / or elsewhere in the application. It will be understood that they are representative of more general processes and / or apparatus and / or technology.

  While specific points of the subject matter described herein are set forth, one of ordinary skill in the art will be able to make changes and modifications based on the techniques described herein without departing from the individual subject matter described or a broader perspective, and Therefore, it will be understood that the appended claims encompass all changes and modifications as fall within the true spirit and scope of the subject matter described herein. In general, one of ordinary skill in the art will understand that terms used herein, particularly those used in the appended claims (eg, the body of the appended claims), are generally intended to be “open” terms. (For example, the term “including” should be interpreted as “including but not limited to”, and the term “having” should be interpreted as “having at least” and “including” And the term “including but not limited to” etc.). Further, those skilled in the art, where a specific number of claims is included, such intentions are expressly stated in the claims and there is no description that such intentions do not exist. You will understand that. For example, as an aid to understanding, the following appended claims may include use of the introductory phrases “at least one” and “one or more” which are introduced into the description of the claims. However, the use of such phrases is such that the introduction of a claim statement by the indefinite article “a” or “an” includes only one such statement in the claim statement. Should not be construed as including limiting the scope of the particular claims including any such introduction. Even if a claim contains “one or more” or “at least one” and an indefinite article such as “a” or “an” (eg, “a” and / or "An" typically should be taken to mean "at least one" or "one or more"); the same definite article used to introduce claim recitations It can also be said that it is used. Further, even if a particular number of introduced claims are explicitly stated, those skilled in the art should understand that such a description should typically be interpreted as at least the stated number. It will be understood (e.g., the description "two descriptions" without other modifiers typically means at least two descriptions, or two or more descriptions). Further, in examples where a convention similar to “at least one of A, B and C, etc.” is used, such a configuration is generally intended in the sense that one of ordinary skill in the art would understand this convention. (For example, “a system having at least one of A, B and C” includes A only, B only, C only, A and B, A and C, B and C, and / or A, B And all of C, etc., but is not limited to this). In examples where a convention similar to “at least one of A, B, C, etc.” is used, such a configuration is generally intended in the sense that one skilled in the art would understand this convention ( For example, “a system having at least one of A, B, or C” includes A only, B only, C only, A and B, A and C, B and C, and / or A, B and C. Including, but not limited to, systems having all of the above). Those of ordinary skill in the art will recognize whether the disjunctive words and / or phrases that represent two or more alternative terms are either in the description, the claims, or the drawings, It will be understood that unless otherwise, it should be understood that the possibility of including one of the terms, any of the terms, or both, is considered. For example, the phrase “A or B” is typically understood to include the possibilities of “A” or “B” or “A and B”.

  With regard to the appended claims, those skilled in the art will appreciate that the operations described herein may generally be performed in any order. Also, although the flow of various operations is shown sequentially, it will be understood that the various operations may be performed in a different order than described, or performed simultaneously. Examples of such alternative instructions include duplicative, alternating, interrupted, realigned, increased, prepared, supplemented, simultaneous, reverse, or other modified instructions unless otherwise indicated. Also, terms such as “in response to”, “in connection with” or other past tense adjectives are generally not intended to exclude such modifications unless otherwise indicated.

  Therefore, a heat exchanger, its method and fission reactor system are provided.

  While various aspects and embodiments have been illustrated herein, other aspects and embodiments will be apparent to those skilled in the art. For example, referring to FIG. 14, shut-off valves 640a / 640b / 650a / 650b are respectively coupled to one of a plurality of thermocouples (not shown) disposed in pipes 620a / 620b / 630a / 630b. May be. The controller can selectively open and close the shut-off valve depending on the temperature of the heat transfer fluid entering or leaving the heat exchanger 600/610. That is, the amount of heat transfer desired within the heat exchanger as a function of the temperature sensed by the thermocouple can be programmed and stored in the controller. The temperature inside the heat exchanger can be sensed by the controller via a thermocouple, after which the controller operates the shut-off valve by progressively opening and closing the shut-off valve, and inside the controller The heat transfer that occurs inside the heat exchanger is caused substantially in harmony with the stored program values. In this way, the heat exchanger 600/610 can be selectively operated to provide an accurate amount of heat transfer within the heat exchanger by the controller automatically adjusting the valves. it can.

  Moreover, the various aspects and embodiments described herein are for illustrative purposes and are not intended to limit the true scope and spirit of which is indicated by the appended claims. Furthermore, the corresponding structure, material, operation and equivalent of all means or step plus function elements of the following claims are intended to perform their functions in combination with other specifically recited claim elements. It is intended to include any structure, material or operation.

1 is a schematic diagram of a fission reactor system. FIG. 3 is a horizontal cross-sectional view of a hexagonal fission reactor core including a plurality of fission reactor modules and a breeder reactor module. FIG. 3 is a horizontal sectional view of one of a plurality of fission reactor modules and a plurality of control rods therein. FIG. 3 is an isometric view of a nuclear fuel rod, with some removed for clarity. It is a horizontal sectional view of a fission reactor core having a parallelepiped shape including a plurality of fission reactor modules and a breeder reactor module. 3 is a vertical cross-sectional view of three exemplary fission reactor modules, partially removed for clarity. FIG. FIG. 3 is an isometric view of a heat exchanger. FIG. 4 is an isometric view of a cross section of the heat exchanger shown in partial appearance. It is an isometric view of a cross section of a heat exchanger showing a guide structure. It is a vertical sectional view of a heat exchanger showing a cross flow of a first heat transfer fluid and a second heat transfer fluid. It is a vertical sectional view of a heat exchanger showing backflow of the 1st heat transfer fluid and the 2nd heat transfer fluid. FIG. 9B is an exploded isometric view of the heat exchanger shown in FIG. 9A showing the backflow of the first heat transfer fluid and the second heat transfer fluid, partially removed for clarity. It is a vertical sectional view of a heat exchanger showing a parallel flow of a first heat transfer fluid and a second heat transfer fluid. FIG. 9D is an exploded isometric view of the heat exchanger shown in FIG. 9C showing a parallel flow of the first heat transfer fluid and the second heat transfer fluid, partially removed for clarity. It is an isometric view of the flow rate having a plurality of blades on its outer surface. It is an isometric view of the flow rate having a plurality of nodes on its outer surface. It is an isometric view of the flow rate having a plurality of blades on its inner surface. FIG. 5 is an isometric view of the flow rate defining a flow path through it and grooves disposed along the flow path. FIG. 6 is an isometric view of the flow rate having edge-shaped blades on its outer surface. It is an isometric view of the flow rate where the density increases toward the outer surface. It is the schematic of the several heat exchanger arrange | positioned at a pressure vessel. FIG. 15 is a view taken along section line 15-15 in FIG. 14. 1 is a horizontal cross-sectional view of a pressure vessel belonging to a fission reactor system showing a plurality of adjacent heat exchangers disposed in the pressure vessel. FIG. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor. It is a flowchart explaining the assembly method of the heat exchanger used corresponding to a nuclear fission nuclear reactor.

Claims (22)

A method of manufacturing a heat exchanger that can be used in a pooled fission reactor and can be placed in a pool fluid existing in the pooled fission reactor, wherein the heat exchanger is located inside a pool wall that encloses the pool fluid. Can be placed in the vicinity of
A method of manufacturing a heat exchanger, comprising receiving a heat exchanger body having a surface formed therein and defining a portion of a plenum volume.   The method of manufacturing a heat exchanger according to claim 1, 12 or 18, characterized in that a part of the plenum volume defined by the surface formed in the heat exchanger body can be occupied by a heat transfer fluid.   19. Manufacturing a heat exchanger according to claim 1, 12 or 18, characterized in that a part of the plenum volume defined by the surface formed in the heat exchanger body can control the flow rate of the heat transfer fluid. Method.   The portion of the plenum volume defined by a surface formed in the heat exchanger body has a predetermined shape for guiding the flow rate of pool fluid through the heat exchanger body. Method of manufacturing a heat exchanger.   The method for manufacturing a heat exchanger according to claim 1 or 12, wherein the surface formed on the heat exchanger body defines a part of the inlet manifold corresponding to a part of the plenum volume.   The method for manufacturing a heat exchanger according to claim 1 or 12, wherein the surface formed on the heat exchanger body defines a part of the outlet manifold corresponding to a part of the plenum volume.   The method of manufacturing a heat exchanger according to claim 1, wherein receiving the heat exchanger body includes receiving a guide structure for guiding a flow rate of the pool fluid.   The method of manufacturing a heat exchanger according to claim 1, wherein receiving the heat exchanger body includes receiving an inlet guide structure for guiding an inlet flow rate of the pool fluid.   The method of manufacturing a heat exchanger according to claim 1, wherein receiving the heat exchanger body includes receiving an outlet guide structure that guides an outlet flow rate of the pool fluid.   The method for manufacturing a heat exchanger according to claim 1, wherein the surface formed on the heat exchanger body has an enhanced plenum volume.   The method of manufacturing a heat exchanger according to claim 1 or 12, wherein receiving the heat exchanger body includes receiving a heat exchanger body without a manifold. A heat exchanger manufacturing method that can be used in a pool fission reactor capable of generating heat and can be placed in a pool fluid existing in the pool fission nuclear reactor. It can be placed near the inner periphery of the pool wall to be confined,
(A) a heat exchanger body defining a plenum volume formed therein for a predetermined flow rate of heat transfer fluid entering the plenum volume, having a surface formed therein and defining a portion of the plenum volume; Receive the heat exchanger body,
(B) A method of manufacturing a heat exchanger, characterized in that a heat transfer member defining a flow path passing therethrough is coupled to a heat exchanger body.   13. The coupling of the heat transfer member includes coupling a heat transfer member configured to achieve a predetermined flow rate of heat transfer fluid entering the heat exchanger body. The manufacturing method of the heat exchanger of description.   13. The method of manufacturing a heat exchanger according to claim 12, wherein coupling the heat transfer member includes coupling a heat transfer member having a groove extending along the flow path.   The method of manufacturing a heat exchanger according to claim 12 or 18, wherein the heat exchanger body has an inlet side, and the inlet side does not have a manifold.   The method of manufacturing a heat exchanger according to claim 12 or 18, wherein the heat exchanger main body has an outlet side, and the outlet side has a manifold.   The heat exchanger of claim 12, wherein coupling the heat transfer member includes coupling a heat transfer member having a wall defining an enhanced heat transfer surface therein. Manufacturing method. A heat exchanger manufacturing method that can be used in a pool fission reactor capable of generating heat and can be placed in a pool fluid existing in the pool fission nuclear reactor. It can be placed near the inner periphery of the pool wall to be confined,
(A) receiving a heat exchanger body formed thereon and having a surface defining a plenum volume shaped for a predetermined flow rate of heat transfer fluid entering the plenum volume;
(B) A plurality of adjacent heat transfer members are connected to the heat exchanger body, and are spaced by a predetermined distance to define a plurality of flow paths between opposing ones of the plurality of adjacent heat transfer members. And the flow rate of the heat transfer fluid passing through the plurality of flow paths is distributed.   Connecting a plurality of adjacent heat transfer members includes connecting a plurality of adjacent heat transfer members configured to achieve a substantially constant flow rate of heat transfer fluid entering the heat exchanger body. The method for manufacturing a heat exchanger according to claim 18, wherein:   The method of manufacturing a heat exchanger according to claim 18, further comprising receiving a reactor vessel coupled to the heat exchanger body and defining a portion of the irregularly shaped outlet plenum volume.   Connecting a plurality of adjacent heat transfer members connects a plurality of adjacent heat transfer members containing at least two heat transfer fluids having a direction selected from a cross flow direction, a counter flow direction and a parallel flow direction. The manufacturing method of the heat exchanger of Claim 18 characterized by the above-mentioned.   Connecting the plurality of adjacent heat transfer members may include at least one of the plurality of adjacent heat transfer members provided therewith a wall defining an enhanced heat transfer surface for increased heat transfer through the wall. The method for manufacturing a heat exchanger according to claim 18, comprising connecting.

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