Source: https://patents.google.com/patent/CN102667955A/en
Timestamp: 2020-01-20 09:23:42
Document Index: 47836387

Matched Legal Cases: ['§ 119', '§ 119', 'application No. 12', 'application No. 12', 'application No. 12', 'application No. 11']

CN102667955A - A heat exchanger, methods therefor and a nuclear fission reactor system - Google Patents
CN102667955A
CN102667955A CN2010800535514A CN201080053551A CN102667955A CN 102667955 A CN102667955 A CN 102667955A CN 2010800535514 A CN2010800535514 A CN 2010800535514A CN 201080053551 A CN201080053551 A CN 201080053551A CN 102667955 A CN102667955 A CN 102667955A
CN2010800535514A
J·D·麦克沃特
希尔莱特有限责任公司
2009-09-25 Priority to US12/586,741 priority Critical
2009-09-25 Priority to US12/586,741 priority patent/US20110075786A1/en
2009-12-15 Priority to US12/653,656 priority
2009-12-15 Priority to US12/653,653 priority
2010-09-22 Application filed by 希尔莱特有限责任公司 filed Critical 希尔莱特有限责任公司
2010-09-22 Priority to PCT/US2010/002604 priority patent/WO2011078872A2/en
2012-09-12 Publication of CN102667955A publication Critical patent/CN102667955A/en
A heat exchanger, methods therefor and a nuclear fission reactor system. The heat exchanger comprises a heat exchanger body defining an exit plenum chamber therein shaped for uniform flow of a hot primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between the heat transfer members. The flow passages open into the exit plenum chamber. Spacing of the heat transfer members by the predetermined distance evenly distributes flow of the primary heat transfer fluid through the flow passages, across the surfaces of the heat transfer members and into the exit plenum chamber. Each heat transfer member defines a flow channel therethrough for flow of a cooler secondary heat transfer fluid. Heat transfer occurs from the hot primary heat transfer fluid to the cooler secondary heat transfer fluid as the primary heat transfer fluid flows through the chamber and as the secondary heat transfer fluid simultaneously flows through the flow channel.
热交換器、为此的方法以及核裂变反应堆系统 Heat exchanger, and a method therefor nuclear fission reactor system
[0001] 交叉參考相关申请 [0001] CROSS REFERENCE TO RELATED APPLICATIONS
[0002] 本申请涉及如下所列申请(“相关申请”）以及要求从如下所列申请中获得最早可用有效申请日的权益(例如，要求非临时专利申请的最早可用优先权日，或要求临时专利申请，以及相关申请的任何和所有父代、祖父代、曾祖父代等申请基于35USC§ 119 (e)的权益)。 [0002] The present application relates to the following listed application ( "Related Application") and the requirements of their right earliest available effective filing date of the application as listed below (e.g., non-provisional patent application claims the earliest available priority date, or Provisional patent applications, and any and all applications related parent, generations grandfather, grandfather interest on behalf of the other application 35USC§ 119 (e)) is. 相关申请以及相关申请的任何和所有父代、祖父代、曾祖父代等申请的所有主题以这样的主题不会与本文的主题相抵触的程度通过引用并入本文中。 All relating to any degree and all parent, generations grandfather, grandfather generation of other application not inconsistent with the subject matter described herein in this application and the related applications Related subject matter is incorporated by reference herein.
[0004] 根据美国专利商标局（USPTO)的非法定要求，本申请构成2009年9月25日提交、发明人为Jon D.McWhirter、发明名称为“A HEAT EXCHANGER, METHODS THEREFOR AND ANUCLEAR FISSION REACTOR SYSTEM (热交換器、有关方法以及核裂变反应堆系统)”的美国专利申请第12/586，741号的部分继续申请，该申请当前同时待审，或者是给予当前同时待审申请以申请日的权益的申请。 [0004] According to the US Patent and Trademark Office (USPTO) non-statutory requirements, the present application constitutes filed September 25, 2009, inventor Jon D.McWhirter, entitled "A HEAT EXCHANGER, METHODS THEREFOR AND ANUCLEAR FISSION REACTOR SYSTEM ( a heat exchanger, and about nuclear fission reactor system method) "continuation in part application of U.S. Patent application No. 12 / 586,741, which application is currently pending, or the pending application of the current administered to the benefit of the filing date Application.
[0005] 根据美国专利商标局（USPTO)的非法定要求，本申请构成2009年12月15日提交、发明人为Jon D. McWhirter、发明名称为“A HEAT EXCHANGER, METHODS THEREFOR AND ANUCLEAR FISSION REACTOR SYSTEM (热交換器、有关方法以及核裂变反应堆系统)”的美国专利申请第12/653，656号的部分继续申请，该申请当前同时待审，或者是给予当前同时待审申请以申请日的权益的申请。 [0005] According to statutory requirements U.S. Patent and Trademark Office (USPTO), the configuration of the present application filed December 15, 2009, by inventors Jon D. McWhirter, entitled "A HEAT EXCHANGER, METHODS THEREFOR AND ANUCLEAR FISSION REACTOR SYSTEM ( a heat exchanger, and about nuclear fission reactor system method) "continuation in part application of U.S. Patent application No. 12 / 653,656, which application is currently pending, or the pending application of the current administered to the benefit of the filing date Application.
[0006] 根据美国专利商标局（USPTO)的非法定要求，本申请构成2009年12月15日提交、发明人为Jon D. McWhirter、发明名称为“A HEAT EXCHANGER, METHODS THEREFOR AND ANUCLEAR FISSION REACTOR SYSTEM (热交換器、有关方法以及核裂变反应堆系统)”的美国专利申请第12/653,653号的部分继续申请，该申请当前同时待审，或者是给予当前同时待审申请以申请日的权益的申请。 [0006] According to statutory requirements U.S. Patent and Trademark Office (USPTO), the configuration of the present application filed December 15, 2009, by inventors Jon D. McWhirter, entitled "A HEAT EXCHANGER, METHODS THEREFOR AND ANUCLEAR FISSION REACTOR SYSTEM ( a heat exchanger, and about nuclear fission reactor system method) "continuation in part application of U.S. Patent application No. 12/653, 653, which application is currently pending, or the pending application of the current administered to the benefit of the filing date of the application.
[0007] 美国专利商标局（USPTO)已经发布了内容是USPTO的计算机程序要求专利申请人引用序号和指示申请是继续申请还是部分继续申请的公告。 [0007] United States Patent and Trademark Office (USPTO) has issued the content is the USPTO's computer programs require that patent applicants reference number and indicating application is a continuation application or part of the continued application of the announcement. 有关细节请參阅可在http: //www. uspto. gov/web/offices/ com/sol/og/2003/weekll/patbene. htm.上查至Ij 的文章Stephen G. Kunin,Benefit of Prior-Filed Application,USPTO Official GazetteMarch 18,2003.本申请实体(下文称为“申请人”）在上面已经提供了如法规所述要求其优先权的申请的特定引用。 For details, refer may at http:.. // www uspto gov / web / offices / com / sol / og / 2003 / weekll / patbene htm check to Ij article on Stephen G. Kunin, Benefit of Prior-.. specific filed application, USPTO Official GazetteMarch 18,2003. the present applicant entity (hereinafter referred to as "applicant") has been provided as above, the regulatory application claims the priority of reference. 本申请人明白，该法规在其特定引用语言上是明确的，不需要序列或像“继续”或“部分继续”那样的任何表征来要求美国专利申请的优先权。 The Applicant has appreciated that the specific reference in its regulation is clear language, undesired sequence or "continue" or "continue moiety" as characterized as any claims priority to U.S. Patent Application. 尽管如上文所述，但本申请人明白，USPTO的计算机程序有某些数据输入要求，因此本申请人将本申请指定成如上所述它的父代申请的部分继续，但应明确指出，这样的指定决不能理解成除了其父代申请的主题之外，本申请是否包含某新主题的任何类型注释和/或承认。 Notwithstanding the above, the present Applicants have appreciated, the USPTO's computer programs have certain data entry requirements, and therefore the applicant of the present application will be designated as part of its parent as described above continue to apply, but it should be clear that this any type of comment must not be understood as specified in addition to the subject matter of its parent application, the application contains a new topic and / or recognition.
[0008] 本申请一般涉及诱发核反应，包括系统、过程和元件(诸如反应堆堆芯、主热交换器或泵)，所述元件浸没在容器中的液体冷却剂中实现这样的过程，并且本申请更具体地涉及热交換器、为此的方法以及核裂变反应堆系统。 [0008] The present application relates generally to induce nuclear reactions, including systems, processes and elements (such as the reactor core, the main heat exchanger or pump), the elements to achieve such a process vessel immersed in a liquid coolant, and this application and more particularly it relates to heat exchangers, and a method therefor nuclear fission reactor system.
[0009] 众所周知，在正在运行的核裂变反应堆中，已知能量的中子被具有大原子质量的核素吸收。 [0009] It is well known in the nuclear fission reactor is running, the known energy neutrons are absorbed species having large atomic mass. 所得到的复合核分解成包括两个较低原子质量裂变碎片以及衰变产物的裂变产物。 The resulting composite core comprises two decomposed into lower atomic mass fission fragments and fission product decay products. 已知通过所有能量的中子经受这样的裂变的核素包括铀-233，铀-235和钚-239，它们是可裂变核素。 Known to undergo such fission by neutrons of all energies include uranium-233 isotope, uranium-235 and plutonium-239, which are fissile nuclides. 例如，具有0.0253eV (电子伏特）的动能的热中子可以用于使U-235核裂变。 For example, thermal neutrons having a kinetic energy of 0.0253eV (electron volts) can be used to fission U-235. 作为可转换核素的钍-232和铀-238将不经历诱发裂变，除非使用具有至少IMeV(百万电子伏特)的动能的快中子。 As switchable radionuclides uranium-238 and thorium-232 will not undergo induced fission, unless at least the fast neutron kinetic energy IMeV (million electron volts). 从每个裂变事件中释放的总动能是大约200MeV。 The total kinetic energy released from each fission event is about 200MeV. 该动能转化为热。 The kinetic energy is converted into heat.
[0010] 在核反应堆中，上述可裂变和/或可转换材料通常容纳在限定核反应堆堆芯的多个紧密捆扎在一起的燃料组件中。 [0010] In a nuclear reactor, fissionable above and / or converting material typically housed in a fuel assembly of the nuclear reactor core defining a plurality of tightly packed together in. 可裂变和/或可转换材料可以是以燃料芯块的形式的铀和钚的氧化物的混合物，该燃料芯块容纳在被隔离物或螺旋形地围绕每根燃料棒缠绕的导线分隔开的燃料棒中。 May be a mixture of fissile and / or fertile material in the form of oxide fuel pellets of uranium and plutonium, the fuel pellets to be accommodated in the spacer or helically wound around each of the fuel rods spaced apart wires the fuel rods.
[0011] 另外，在商用核动カ反应堆中，将裂变热转化成电。 [0011] Further, the commercial grades of nuclear reactors, the fission heat into electricity. 关于这方面，通过限定反应堆堆芯的反应堆燃料组件抽运和通过裂变过程加热反应堆一次冷却剤。 In this regard, defined by reactor fuel assembly and reactor core heating reactor pumping primary cooling Ji by the fission process. 在一些反应堆设计中，将加热的一次冷却剂传送到蒸汽发生器，在蒸汽发生器中加热的一次冷却剂将它的热量交给布置在蒸汽发生器中的二次冷却剂（即，水)。 In some reactor designs, the heated primary coolant is transferred to the steam generator, the primary coolant in the steam generator is heated to its heat to the secondary coolant in the steam generator is disposed (i.e., water) . 然后一次冷却剂返回到反应堆堆芯。 Primary coolant is then returned to the reactor core. 接收一次冷却剂热量的一部分水蒸发成蒸汽，该蒸汽行进到涡轮发电机组以便发电。 A heat receiving portion of the coolant water evaporated into steam, which travels to the turbine generator for power generation. 已经通过涡轮发电机组的蒸汽流到冷凝器，冷凝器使蒸汽凝结成水，水然后返回到蒸汽发生器。 Flows to the condenser has a steam turbine generator set by the condenser so that steam is condensed into water, and then returns to the steam generator.
[0012] 能够安全发电的一种核裂变反应堆是池式液态钠快中子増殖反应堆。 [0012] A nuclear fission reactor power generation is safe pool-type liquid sodium reactor fast zo proliferation. 在这点上，铀-238可以用作可转换材料。 In this regard, uranium-238 may be used as conversion material. 铀-238吸收中子，并且依靠β衰变蜕变成可裂变钚-239。 U-238 neutron absorption, and relies on β decay transformed into fissile plutonium-239. 当钚-239又吸收中子时，发生产生热量的裂变。 When the plutonium-239 and absorb neutrons, fission heat generation. 在快中子増殖反应堆中，可能不希望诸如水的慢化材料作为冷却剤。 In a fast neutron reactor zo proliferation may be undesirable material, such as slow as the cooling water Ji. 而是，在这样的池式液态钠快中子増殖核反应堆中，钠是选择的冷却剤，因为钠不使中子显著热化。 Instead, such a pool-type liquid sodium in a fast neutron nuclear reactor zo proliferation, sodium cooling Ji chosen as sodium neutrons without significant heating. 此外，由于钠的传热特性，反应堆堆芯可以以较高功率密度运行，使得可以缩小反应堆的尺寸。 Further, since the heat transfer characteristics of the sodium, the reactor core can operate at higher power densities, so that the reactor can be downsized. 另外，钠在大约100° C (大约212° F)熔化以及在大约900° C (大约1650° F)沸腾。 Further, the sodium melting at about 100 ° C (about 212 ° F) and boils at about 900 ° C (about 1650 ° F). 因此，可以在高温使用钠而不沸腾，从而允许生成高温高压蒸汽。 Thus, instead of sodium boiling at a high temperature so as to allow steam to generate high temperature and pressure. 这又提供了提高的电厂热效率。 This in turn provides improved thermal power plant efficiency.
[0013] 然而，循环通过反应堆堆芯的钠冷却剂由于吸收中子而变成放射性的。 [0013] However, sodium is circulated through the reactor core coolant by absorbing neutrons become radioactive. 由于这种放射性，反应堆设计者利用（多个）一次钠冷却剂环路与蒸汽发生环路之间的中间热交换环路。 Due to this radiation, the designer using the reactor (s) with a sodium coolant loop steam generation loop between the intermediate heat exchange loop. 这降低了涡轮发电机的放射性污染的风险。 This reduces the risk of radioactive contamination of the turbine generator. 另外，可能出现蒸汽发生器管道泄漏。 Further, the steam generator tube leak may occur. 如果在将钠传送通过蒸汽发生器的管道系统中出现泄漏，则通过蒸汽发生器的热放射性钠将与蒸汽发生器中的水和蒸汽剧烈化学反应。 If a leak occurs in the piping system through the transfer of sodium in the steam generator, the steam generator through the thermal chemical radioactive sodium vigorous reaction with the steam generator and the water vapor. 这将放射性地污染蒸汽发生器中的水和蒸汽，从而增加了周围生物圏的放射性污染的风险。 This will radioactively contaminated steam generator and the water vapor, thereby increasing the risk of radioactive contamination of the surrounding rings of organisms. 由于上述的原因，反应堆设计者在反应堆堆芯与蒸汽生发生器之间加入中间热交換器的使用，以避免堆芯中的钠与蒸汽发生器或涡轮发电机的直接接触。 For the above reasons, the designers of the reactor was added the intermediate heat exchanger between the reactor core and the steam generator green, to avoid direct contact with the core sodium in the steam generator or turbine generator.
[0014] 因此，在上述的池式液态钠快中子増殖核反应堆中，中间热交換器形成反应堆池中的放射性一次钠与蒸汽发生器中的非放射性二次钠之间的边界。 [0014] Thus, in the above formula pool of liquid sodium in a fast neutron nuclear reactor enlargement of colonization, the intermediate heat exchanger forms a boundary between the non-radioactive secondary sodium pool reactor radioactive primary sodium in the steam generator. 换句话说，与反应堆堆芯一起布置在液态钠池中的中间热交換器通常用于从快中子増殖反应堆堆芯中去热，并将该热量传递给外部蒸汽发生器。 In other words, the reactor core is disposed in the intermediate heat exchanger with the pool of liquid sodium generally used for removing heat from the reactor core neutron enlargement of proliferation, and the heat is transferred to the external steam generator.
[0015] 已经进行尝试，以便通过利用中间热交換器提供热量从快中子裂变核反应堆堆芯的充分移除。 [0015] Attempts have been made to provide adequate heat removal from the fast fission nuclear reactor core by using the intermediate heat exchanger. 1981年10月13日以Peter Humphreys等人的名义颁发和发明名称为“Nuclear Reactors (核反应堆)”的美国专利第4，294, 658号公开了ー种中间热交换模块，该中间热交换模块包含壳管式中间交換器和电磁流耦合器，其布置在用于驱动一次冷却剂通过热交換器的模块的基本区域中。 October 13, 1981 in the name of Peter Humphreys et al., Issued and entitled "Nuclear Reactors (reactor)," U.S. Patent 4,294, 658 discloses a heat exchange module ー intermediate species, the intermediate heat exchange module comprising the intermediate shell and tube exchangers and the electromagnetic flow coupler, which is arranged for driving the primary coolant through the heat exchanger module in the basic region. 该专利处理了当在相关二次冷却剂回路中的冷却剂流中存在中断，例如，如由二次冷却剂泵的故障引起时，对中间热交換器造成的严重热冲击。 The patent dealt with when the coolant flow in the associated secondary coolant circuit is interrupted in the presence of, for example, caused by a malfunction such as when the secondary coolant pump, the intermediate heat exchanger to cause severe thermal shock. 根据该专利，该发明的目的是在二次冷却剂回路中的流中存在中断的这种紧急情况下，减轻对池式的液态金属冷却核反应堆的中间热交換器造成的热冲击。 According to this patent, the object of the invention is a thermal shock in such an emergency case the secondary flow in the coolant circuit interruption exists, the intermediate heat exchanger to reduce the liquid metal cooled pool type nuclear reactor caused.
[0016] 在1982年4月13日以Michael G. Sowers等人的名义颁发和发明名称为“Intermediate Heat Exchanger For A Liquid Metal Cooled Nuclear Reactor AndMethod (液态金属冷却核反应堆的中间热交換器及其方法)”的美国专利第4，324，617号中公开了另一种尝试，该尝试通过使用中间热交換器提供热量从快中子裂变核反应堆堆芯中的充分移除。 [0016] in the name of Michael G. Sowers et al., Issued and entitled "(the intermediate heat exchanger and a method for liquid metal cooled nuclear reactor) Intermediate Heat Exchanger For A Liquid Metal Cooled Nuclear Reactor AndMethod on April 13, 1982 "U.S. Patent No. 4,324,617 discloses another attempt, the attempt by the intermediate heat exchanger provides heat from the fast fission nuclear reactor core sufficiently removed. 该专利公开了ー种用在多池、液态金属冷却核反应堆中的热交換器。 This patent discloses a multi-cell ー species for use in liquid metal-cooled nuclear reactor heat exchanger. 该专利处理了调和（accommodate)热交換器的各结构组件之间的差别热膨胀。 This patent addressed the thermal difference between the harmonic components of the structure (Accommodate) expansion of the heat exchanger. 按照这个专利，通过与热池的热连通将热交換器的壳体加热到明显高于热交換器中的管道温度的温度，在运行期间通过壳体的所述加热拉伸所述管道，从而调和热交換器中的差别热膨胀。 According to this patent, the hot sink in thermal communication with the housing of the heat exchanger is heated to a temperature significantly higher than the piping temperature of the heat exchanger, heat-stretching during operation of the duct through the housing, whereby reconcile the differences in the thermal expansion of the heat exchanger.
[0017] 尽管上文列举的技术可能公开了足以服务它们意图的目的的设备和方法，但上文列举的技术没有一种看起来公开了如本文所述和请求保护的热交換器、为此的方法以及核裂变反应堆系统。 [0017] Although the techniques listed above may disclose an apparatus and method sufficient to service their intended purpose, but none of the techniques mentioned above appear to disclose a heat exchanger as described herein and claimed, for this the nuclear fission reactor system and method.
[0018] 按照本公开的ー个方面，提供了一种与能够发热的池式核裂变反应堆关联使用、能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器，所述热交換器能够布置在限制池流体的池壁的内围附近，所述热交換器包含：热交換器主体；以及与所述热交換器主体形成整体以便去热的装置。 [0018] According to the present disclosure ー aspect, there is provided a cell associated with the nuclear fission reactor can be used to heat, the heat exchanger can be disposed in the fluid reservoir resides in pool type nuclear fission reactor in the the heat exchanger can be disposed in the vicinity of the pool confining fluid limits the wall, the heat exchanger comprising: a heat exchanger body; and the whole device so as to heat the heat exchanger body is formed.
[0019] 按照本公开的ー个另外方面，提供了一种与能够发热的池式核裂变反应堆关联使用、能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器，所述热交換器能够布置在限制池流体的池壁的内围附近，所述热交換器包含具有在其上形成的限定容腔(plenum volume)的一部分的表面的热交换器主体。 [0019] According to the present disclosure ー a further aspect, there is provided a nuclear fission reactor and associated cell capable of generating heat, the heat exchanger can be disposed in the fluid reservoir resides in pool type nuclear fission reactor in, the said heat exchanger is disposed in the vicinity of the pool confining fluid limits the wall, the heat exchanger comprising a body portion having a surface defining a cavity (plenum volume) formed thereon.
[0020] 按照本公开的ー个进一歩方面，提供了一种与能够发热的池式核裂变反应堆关联使用、能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器，所述热交換器能够布置在限制池流体的池壁的内围附近，所述热交換器包含：将容腔限定在其中的热交換器主体，所述容腔被做成使传热流体预定流入容腔中的形状，所述热交換器主体具有在其上面形成、限定容腔的该部分的表面；以及与所述热交換器主体耦合的传热构件，所述传热构件限定从中通过的流动通道。 [0020] According to the present disclosure ー into a ho th aspect, a cell associated with the nuclear fission reactor can be used to heat, the heat exchanger can be disposed in the fluid reservoir resides in pool type nuclear fission reactor in, the heat exchanger is disposed in the vicinity of the pool confining fluid limits the wall, the heat exchanger comprising: a heat exchanger body cavity defined therein, the cavity being made a predetermined heat transfer fluid the shape of the inflow chamber, the heat exchanger has a body formed thereon, the surface portion defining a cavity; and a heat transfer member coupled to the body of the heat exchanger, the heat transfer member therethrough defined by flow channel.
[0021] 按照本公开的ー个另外方面，提供了一种与能够发热的池式核裂变反应堆关联使用、能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器，所述热交換器能够布置在限制池流体的池壁的内围附近，所述热交換器包含：具有在其上形成的限定容腔的一部分的表面的热交換器主体，所述容腔被做成使传热流体预定流入容腔的该部分中的形状；以及与所述热交換器主体连接并隔开预定距离的多个相邻传热构件，用于限定所述多个相邻传热构件的相对传热构件之间的多条流动通路，用于分发传热流体流动通过多条流动通路。 [0021] According to the present disclosure ー a further aspect, there is provided a nuclear fission reactor and associated cell capable of generating heat, the heat exchanger can be disposed in the fluid reservoir resides in pool type nuclear fission reactor in, the said heat exchanger is disposed in the vicinity of the pool confining fluid limits the wall, the heat exchanger comprising: a heat exchanger main body portion of the surface defining a cavity formed thereon, said cavity being made heat transfer fluid flows into the predetermined shape of the portion of the chamber; and a heat transfer member connected to the heat exchanger body and a plurality of adjacent spaced apart a predetermined distance for defining a plurality of adjacent heat transfer a plurality of flow paths between the heat transfer member opposing member, for distributing the heat transfer fluid flow through multiple flow paths.
[0022] 按照本公开的ー个方面，提供了一种与池式核裂变反应堆关联使用的系统，其包含：能够发热的核裂变反应堆堆芯；与所述核裂变反应堆堆芯相联系的热交換器主体，所述热交換器主体能够布置在池流体中和限制池流体的池壁的内围附近；以及与所述核裂变反应堆堆芯传热连通和与所述热交換器主体相联系以便去热的装置。 [0022] According to the present disclosure ー aspect, there is provided a system associated with the pool type nuclear fission reactor use, comprising: a heat capable of nuclear fission reactor core; heat associated with the nuclear fission reactor core exchanger body, the heat exchanger can be arranged in a body fluid tank and limiting the wall near the inner circumference of the fluid tank; and associated with said heat transfer communication with the nuclear fission reactor core and the heat exchanger body so that the heat removing means.
[0023] 按照本公开的另ー个方面，提供了一种与池式核裂变反应堆关联使用的系统，其包含：限定具有内围的池壁的容器，该池壁被配置为将池流体限定在其中；能够布置在所述容器中和能够发热的核裂变反应堆堆芯；能够与所述核裂变反应堆堆芯传热连通的热交换器主体，所述热交換器主体能够布置在池流体中和池壁的内围附近，所述热交換器主体具有在其上面形成的限定容腔的一部分的表面，所述容腔被做成实现传热流体进入容腔中的预定流动的形状；以及与所述核裂变反应堆堆芯传热连通和与所述热交換器主体相联系以便去热的装置。 [0023] The present disclosure further ー aspect, there is provided a system associated with the pool type nuclear fission reactor used in accordance comprising: a container defining an inner periphery of the wall, the wall of the fluid reservoir is configured to define therein; can be disposed in the container and capable of heating the nuclear fission reactor core; heat exchanger body can be in communication with the nuclear fission reactor core heat exchanger body can be disposed in the fluid reservoir and near the inner circumference of the wall, the heat exchanger having a surface portion of the body defining a cavity formed thereon, said cavity being made to achieve a heat transfer fluid flowing into the predetermined shape of the cavity; and associated with said body so as to heat exchanger means in communication with the nuclear fission reactor core and heat transfer.
[0024] 按照本公开的ー个另外方面，提供了一种与池式核裂变反应堆关联使用的系统，其包含：限定具有内围的池壁的压カ容器，该池壁被配置为将池流体限定在其中；布置在所述压カ容器中和能够发热的核裂变反应堆堆芯；能够与所述核裂变反应堆堆芯传热连通的热交換器主体，所述热交換器主体能够布置在池流体中和池壁的内围附近，所述热交換器主体具有在其上面形成、将容腔的一部分限定在其中的表面，所述容腔被做成使传热流体预定流入容腔中的形状；以及与所述热交換器主体耦合和隔开预定距离的多个相邻传热构件，用于限定所述多个相邻传热构件的相对传热构件之间的多条流动通路，用于分发传热流体流动通过多条流动通路。 [0024] According to the present disclosure ー a further aspect, there is provided a system for pool-type reactor is associated with the use of nuclear fission, comprising: defining a pressure vessel surrounding the grades of the wall, the wall of the tank configured to defining a fluid therein; ka disposed in the pressure vessel and heat generation can be nuclear fission reactor core; can be the reactor core body of the heat exchanger in heat transfer communication with the nuclear fission, the heat exchanger can be arranged in the body and a fluid reservoir near the inner circumference of the wall, the heat exchanger has a body formed thereon, a portion of the surface defining the chamber therein, said chamber being made so that the heat transfer fluid flows into the chamber in a predetermined shape; and a heat transfer member coupled to the heat exchanger body and a plurality of adjacent spaced apart a predetermined distance for defining a plurality of said plurality of flow paths between the heat transfer member relative to an adjacent heat transfer member , for distributing the heat transfer fluid flow through multiple flow paths.
[0025] 按照本公开的ー个进一歩方面，提供了一种为了与能够发热的池式核裂变反应堆关联使用，组装能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器的方法，所述热交換器能够布置在限制池流体的池壁的内围附近，所述方法包含：接收热交換器主体；以及将装置与热交換器主体耦合用于去热。 [0025] According to the present disclosure ー into a ho th aspect, there is provided a heat exchanger associated with the use of one kind for pool-type nuclear fission reactor capable of generating heat, the assembly can be disposed in the fluid reservoir resides in pool type nuclear fission reactor in 's method, the heat exchanger can be disposed in the vicinity of the inner peripheral limits of the wall of the fluid reservoir, the method comprising: receiving the main heat exchanger; and means for coupling the body to the heat exchanger.
[0026] 按照本公开的ー个方面，提供了一种为了与能够发热的池式核裂变反应堆关联使用，组装能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器的方法，所述热交换器能够布置在限制池流体的池壁的内围附近，所述方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 [0026] According to the present disclosure ー aspect, there is provided a heat exchanger associated with the reactor in order to use the pool of the nuclear fission heat can be assembled in the cell can be disposed in the fluid reservoir resides in the nuclear fission reactor in the the method of the heat exchanger can be disposed in the vicinity of the pool confining fluid limits the wall, comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of.
[0027] 按照本公开的ー个方面，提供了一种为了与能够发热的池式核裂变反应堆关联使用，组装能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器的方法，所述热交换器能够布置在限制池流体的池壁的内围附近，所述方法包含：接收将容腔限定在其中的热交換器主体，所述容腔被做成使传热流体预定流入容腔中的形状，所述热交換器主体具有在其上面形成的限定容腔的一部分的表面；以及将传热构件与热交換器主体耦合，所述传热构件限定从中通过的流动通道。 [0027] According to the present disclosure ー aspect, there is provided a heat exchanger associated with the reactor in order to use the pool of the nuclear fission heat can be assembled in the cell can be disposed in the fluid reservoir resides in the nuclear fission reactor in the the method of the heat exchanger can be disposed in the vicinity of the inner peripheral limits of the wall of the fluid reservoir, the method comprising: receiving a heat exchanger body cavity defined therein, said cavity being made of a heat-transfer fluid flows into the predetermined shape of the cavity, the heat exchanger having a surface portion of the body defining a cavity formed thereon; and a heat transfer member coupled to the main heat exchanger, the heat transfer member defining a flow therethrough of aisle.
[0028] 按照本公开的另ー个方面，提供了一种为了与能够发热的池式核裂变反应堆关联使用，组装能够布置在驻留在池式核裂变反应堆中的池流体中的热交換器的方法，所述热交換器能够布置在限制池流体的池壁的内围附近，所述方法包含：接收具有在其上形成的限定容腔的一部分的表面的热交換器主体，所述容腔被做成使传热流体预定流入容腔中的形状；以及将多个相邻传热构件与所述热交換器主体连接，所述多个相邻传热构件隔开预定距离，用于限定所述多个相邻传热构件的相对传热构件之间的多条流动通路，用于分发传热流体流动通过多条流动通路。 [0028] According to another aspect ー present disclosure, there is provided a heat exchanger associated with the cell in order to use nuclear fission reactor capable of generating heat, the assembly can be disposed in the fluid reservoir resides in pool type nuclear fission reactor in near the inner periphery, the method of the method, the heat exchanger can be arranged to limit the pool of fluid, the wall comprising: receiving a portion of the heat exchanger body having a surface defining a cavity formed thereon, said container the chamber is made to flow into a predetermined shape so that a heat transfer fluid in the chamber; and a plurality of adjacent heat transfer member connected to the heat exchanger body, a plurality of adjacent heat transfer members spaced apart a predetermined distance, for defining a plurality of said plurality of flow paths between the heat transfer member relative to an adjacent heat transfer member, for distributing the heat transfer fluid flow through multiple flow paths.
[0029] 本公开的ー个特征是提供将腔室限定在其中的热交換器主体，所述腔室被做成使传热流体均匀流过腔室的形状。 [0029] The present disclosure is to provide ー features defined in the chamber of the heat exchanger body wherein the chamber is made uniform so that heat transfer fluid flows through the shape of the chamber.
[0030] 本公开的另ー个特征是提供与热交換器主体连接并隔开预定距离的多个相邻传热构件，用于限定所述多个相邻传热构件的各自传热构件之间的多条流动通路，以便使传热流体均匀地分散流过所述多条流动通路。 [0030] Another ー present disclosure is to provide a heat exchanger wherein the body is connected and spaced a predetermined distance from the plurality of adjacent heat transfer member, for each of said heat transfer member defining a plurality of heat transfer members adjacent to the a plurality of flow passages between, so as to uniformly disperse the heat transfer fluid flow through the plurality of flow paths.
[0031] 除了上文之外，在本公开的像正文(例如，权利要求书和/或详细描述)那样的讲述和/或附图中展示和描述了各种其它方法和/或设备方面。 [0031] In addition to the above, in and / or aspects of the present disclosure as text (e.g., claims and / or described in detail) such as a talk show or the drawings and described in various other methods and / or devices.
[0032] 上文是ー个总结，因此可能包含细节的简化、概括、蕴含、和/或省略；因此，本领域的普通技术人员应该懂得，该总结只是例示性的，而决不是打算限制本发明的范围。 [0032] The foregoing is ー a summary and thus may contain simplifications, generalizations, contains, and / or omitted; Accordingly, those of ordinary skill in the art should appreciate that the summary is merely illustrative in nature and is in no way intended to limit the scope of the invention. 除了上述的例示性方面、实施例、和特征之外，通过參考附图和如下详细描述，将使进ー步的方面、实施例、和特征变得显而易见。 In addition to the above-described exemplary aspect of the embodiment, other than embodiments, and features of the embodiments, by reference to the drawings and the following detailed description, will step into ー aspects, embodiments, and features will become apparent from the embodiments.
[0033] 虽然本说明书以特别指出和不同地声明本公开的主题的权利要求书作为结论，但相信本公开可以从结合附图所作的如下详细描述中得到更好理解。 [0033] While the specification particularly point out and claim the claimed subject matter of the present disclosure differently from the claims as a conclusion, it is believed that the following detailed description of the present disclosure can be taken from the obtained better understood in conjunction with the accompanying drawings. 另外，用在不同图形中的相同符号通常表示相似或相同的项目。 Further, with the same reference numerals in different drawings typically indicates similar or identical items.
[0034] 图I是核裂变反应堆系统的示意性表示； [0034] FIG. I is a schematic representation of a nuclear fission reactor system;
[0035]图2是包含多个核裂变反应堆模块和増殖燃料模块的六边形状核裂变反应堆堆芯的水平剖视图； [0035] FIG. 2 is a module comprising a plurality of nuclear fission reactor fuel module proliferation and enlargement of the horizontal shape of the nuclear fission reactor core of a hexagonal cross-sectional view;
[0036] 图3是多个核裂变反应堆模块之一和其中的多根控制棒的水平剖视图； [0036] FIG. 3 is one of a plurality of nuclear fission reactor modules wherein a plurality of control rods and a horizontal cross-sectional view;
[0037] 图4是为了清楚起见部分已除去的核燃料棒的等距视图； [0037] FIG. 4 is a section has been removed for clarity, of an isometric view of a nuclear fuel rod;
[0038]图5是包含多个核裂变反应堆模块和増殖燃料模块的平行六面体状核裂变反应堆堆芯的水平剖视图； [0038] FIG. 5 is a nuclear fission reactors comprising a plurality of parallel modules proliferation and enlargement of the fuel module hexahedral nuclear fission reactor core of a horizontal cross-sectional view;
[0039] 图6是为了清楚起见部分已除去的三个示范性核裂变反应堆模块的垂直剖视图； [0039] FIG. 6 is a vertical sectional view for three exemplary nuclear fission reactor module section has been removed the sake of clarity;
[0040] 图7是热交換器的等距视图； [0040] FIG. 7 is an isometric view of the heat exchanger;
[0041] 图8是剖视的和部分虚拟示出的热交換器的等距视图； [0041] FIG. 8 is a cross-sectional view of portions of the virtual and the heat exchanger shown in isometric view;
[0042] 图8A是剖视的和示出引导结构的热交換器的等距视图； [0043] 图9是热交換器的垂直剖视图，这个视图示出了一次传热流体和二次传热流体的交叉流动； [0042] FIG. 8A is a cross-sectional view illustrating a heat exchanger and an isometric view of the guide structure; [0043] FIG. 9 is a vertical sectional view of a heat exchanger, this view shows a heat transfer fluid and a second passage cross-flow heat transfer fluid;
[0044] 图9A是热交換器的垂直剖视图，这个视图示出了一次传热流体和二次传热流体的相向流动； [0044] FIG. 9A is a vertical sectional view of a heat exchanger, this view shows the flow of a heat transfer fluid and opposite the secondary heat transfer fluid;
[0045] 图9B是为了清楚起见部分已除去的显示在图9A中的热交換器的分解等距例示图，这个视图示出了一次传热流体和二次传热流体的相向流动； [0045] FIG. 9B is a section has been removed for clarity, of the heat exchanger displayed in Fig. 9A is an exploded isometric view illustrating, this view shows the flow of a heat transfer fluid and opposite the secondary heat transfer fluid;
[0046] 图9C是热交換器的垂直剖视图，这个视图示出了一次传热流体和二次传热流体的同向流动； [0046] FIG. 9C is a vertical sectional view of a heat exchanger, this view shows the same heat transfer fluid and the secondary heat transfer fluid to flow;
[0047] 图9D是为了清楚起见部分已除去的显示在图9C中的热交換器的分解等距例示图，这个视图示出了一次传热流体和二次传热流体的同向流动； [0047] FIG 9D is a section has been removed for clarity exploded isometric of the heat exchanger in the embodiment shown in FIG. 9C to FIG, this view shows the same heat transfer fluid flows and the secondary heat transfer fluid;
[0048] 图10是在其外表面上具有多个散热片（fin)的传热构件的等距视图； [0048] FIG. 10 is an isometric view of a heat transfer member having a plurality of fins (FIN) in its outer surface;
[0049] 图11是在其外表面上具有多个结的传热构件的等距视图； [0049] FIG. 11 is an isometric view of a heat transfer member having a plurality of nodes on its outer surface;
[0050] 图12是在其内表面上具有多个散热片的传热构件的等距视图； [0050] FIG. 12 is an isometric view of a heat transfer member having a plurality of fins on its inner surface;
[0051] 图13是限定从中通过的流动通道和沿着流动通道布置的多根导管的传热构件的等距视图； [0051] FIG. 13 is a flow passage defined therethrough and an isometric view of a plurality of heat transfer members disposed along the conduit flow path;
[0052]图13A是在其外表面上具有多个楔形散热片的传热构件的等距视图； [0052] FIG 13A is an isometric view of a heat transfer member having a plurality of wedge-shaped fins on its outer surface;
[0053] 图13B是在其外表面上具有増大密度的结的传热构件的等距视图； [0053] FIG. 13B is an isometric view of the enlargement of the heat transfer member having a high density of nodes on its outer surface;
[0054] 图14是布置在压カ容器中的多个热交換器的示意性例示图； [0054] FIG. 14 is disposed in the pressure ka schematic diagram illustrating a plurality of heat exchanger vessel;
[0055] 图15是沿着图14的剖面线15-15截取的视图； [0055] FIG. 15 is a sectional view taken along the line 15-15 in FIG. 14 view;
[0056] 图16是属于核裂变反应堆系统的压カ容器的水平剖视图，这个视图示出了布置在压カ容器中的多个相邻热交換器；以及 [0056] FIG. 16 is a horizontal system belonging to the nuclear fission reactor pressure vessel ka sectional view, this view shows a plurality of adjacent heat exchanger is arranged in a pressure vessel ka; and
[0057] 图17-47是为了与核裂变反应堆关联使用、组装热交換器的例示性方法的流程图。 [0057] FIG. 17-47 for use associated with a nuclear fission reactor, a flow chart illustrating an exemplary method of assembling the heat exchanger of the embodiment.
[0058] 在如下详细描述中，将參考形成其一部分的附图。 [0058] In the following detailed description, with reference to the accompanying drawings which form a part. 在这些附图中，相似的符号通常表示相似的部件，除非上下文另有規定。 In the drawings, similar symbols typically identify similar components, unless context dictates otherwise. 描述在详细描述、附图和权利要求书中的例示性实施例并不意味着限制本发明的范围。 Described in the detailed description, claims and from the accompanying drawings of illustrative embodiments are not meant to limit the scope of the invention. 可以不偏离本文展示的主题的精神或范围地利用其它实施例，以及可以作出其它改变。 May not departing from the subject matter presented herein use the spirit or scope of other embodiments and other changes can be made.
[0059] 另外，为了清晰地展示起见，本申请使用了形式上的概括性标题。 [0059] In addition, in order to clearly show purposes, the application uses the general heading of form. 但是，应该明白，这些概括性标题用于展示的目的，可以在整个申请中讨论不同类型的主题(例如，可以在过程/操作标题下描述设备/结构和/或可以在结构/过程标题下讨论过程/操作；和/或单个话题的描述可以跨越两个或更多个话题标题)。 However, it should be understood that these titles for general purposes of illustration, may be a different type of subject matter discussed throughout the application (e.g., the device can / configuration and / or may be discussed under structure / header process is described in process / operating title process / operation; and / or description of a single topic may span two or more topic titles). 因此，形式上的概括性标题的使用决不是打算限制本发明的范围。 Thus, using the general form of the title is in no way intended to limit the scope of the present invention.
[0060] 此外，本文所述的主题有时例示了包含在其它不同部件内，或与其它不同部件连接的不同部件。 [0060] In addition, subject matter described herein sometimes illustrates different components contained within other different components, or with various other components. 应该明白，这样描绘的架构仅仅是例示性的，事实上，可以实现许多实现相同功能的其它架构。 It should be understood that such depicted architectures are merely exemplary and, in fact, many other architectures can be implemented to achieve the same functionality. 从概念上来讲，有效地“联系”实现相同功能的部件的任何安排，以便实现所希望功能。 Conceptually, effectively "links" to achieve the same functions as any arrangement of components to achieve the desired functionality. 因此，本文组合在一起实现特定功能的任何两个部件可以看作相互“联系”，使得与架构或中间部件无关地实现所希望功能。 Therefore, this combination of any two components together to achieve a particular functionality can be seen as another "link", such that the intermediate member irrespective of architectures or to achieve the desired functionality. 同样，如此联系的任何两个部件也可以视作实现所希望功能的相互“可操作地连接”或“可操作地耦合”，以及能够如此联系的任何两个部件也可以视作实现所希望功能的相互“可操作耦合”。 Likewise, any two components so associated can also be viewed as one another to achieve the desired "operably linked" function or "operably coupled", and any two components capable of being so associated can also be viewed as achieving the desired function mutual "operably coupled." 可操作耦合的特例包括但不限于物理上可配对和/或物理上相互作用部件、可无线相互作用和/或无线相互作用部件、和/或逻辑上相互作用和或/逻辑上可相互作用部件。 Specific examples of operably couplable include but are not limited to physically mateable and / or physically interacting components may be wireless interaction may interact and / or wirelessly interacting components, or interaction, and / or logical and / or logical components .
[0061] 在一些情况下，一个或多个部件在本文中可能被称为“配置为”，“可配置为”，“可 [0061] In some cases, one or more components may be referred to herein as "configured to," "configurable to," "may be
起......作用/起......作用”，“适用干/可适用干”，“能够”，“可依照/依照”等。本领 ...... role played / play role ...... "," suitable for dry / dry applicable "," could "," may be in accordance with / in accordance with ", etc. art
域的普通技术人员应该认识到，“配置为”一般可以包含活动状态部件、非活动状态部件和/或等待状态部件，除非上下文另有要求。 Of ordinary skill in the art will be appreciated, "configured to" may generally comprise active components, inactive components and / or standby state components, unless context requires otherwise.
[0062] 因此，參照图1，只举例而非限制性地示出了统称为10的池式快中子核裂变反应堆和系统。 [0062] Thus, referring to FIG. 1, not limiting example only shows a pool-type fast collectively nuclear fission reactors and system 10. 如下文更详细所述，核裂变反应堆系统10可以是“行波”核裂变反应堆系统。 As described in greater detail below, the system of the nuclear fission reactor 10 may be a "traveling wave" nuclear fission reactor system. 核裂变反应堆系统10产生在多条输电线(未不出）上输送给电カ用户的电力。 The nuclear fission reactor system 10 generates a plurality of transmission lines (not not) conveying electrical power to the user ka. 核裂变反应堆系统10可替代地可以用于进行像确定温度对反应堆材料的影响的测试那样的测试。 Nuclear fission reactor system 10 may alternatively be used to determine the effect of temperature on the reactor as the material of the test as a test.
[0063] 參照图1，2和3，核裂变反应堆系统10包含统称为20的核裂变反应堆堆芯，核裂变反应堆堆芯20包括多个核裂变燃料组件，或也如本文所称，核裂变模块30。 [0063] Referring to FIGS. 1, 2 and 3, system 10 includes a nuclear fission reactor referred to as a nuclear fission reactor core of the nuclear fission reactor core 20 includes a plurality 20 of nuclear fission fuel assembly, or also referred to herein as the nuclear fission module 30. 核裂变反应堆堆芯20被密封地存放在核反应堆堆芯外壳40内，只举例而非限制性地，每个核裂变模块30可以形成如图所示，横截面是六边形状的结构，以便与像圆柱或圆球形状那样核裂变模块30的其它形状相比，可以在反应堆堆芯20内将更多的核裂变模块30紧密堆放在一起。 The nuclear fission reactor core 20 is sealingly stored in a nuclear reactor core within a shell 40, only of example and not limitation, nuclear fission each module 30 may be formed as shown, a hexagonal shaped cross section structure, so as like other cylindrical shape or spherical shape of the nuclear fission module 30 as compared to the reactor core 20 may be within the nuclear fission module 30 more closely stacked together. 每个核裂变模块30包含由于上述链式核裂变反应过程而发热的多根燃料棒50。 Each module 30 includes nuclear fission nuclear fission chain reaction of the above processes a plurality of fuel rods 50 generate heat. 如果需要的话，可以用燃料棒罐60围住多根燃料棒50，以便增加核裂变模块30的结构硬度，以及当核裂变模块30被布置在核裂变反应堆堆芯20中时，将核裂变模块30相互分开。 If desired, a plurality of fuel rods 50 may be surrounded by fuel rods tank 60, in order to increase structural rigidity of the nuclear fission module 30, and when the module 30 is disposed nuclear fission 20 when the nuclear fission reactor core, the nuclear fission module 30 separated from each other. 将核裂变模块30相互分开避免了燃料棒50之间的横向冷却剂交叉流动。 The nuclear fission module 30 laterally spaced from each other to avoid the coolant cross-flow between the fuel rods 50. 避免横向冷却剂交叉流动防止了燃料棒50的横向振动。 To avoid lateral coolant cross-flow preventing lateral vibration of the fuel rods 50. 要不然这样的横向振动可能增加损害燃料棒50的风险。 Otherwise such transverse vibration may increase the risk of damage to the fuel rods 50. 另夕卜，将核裂变模块30相互分开可以使我们逐个模块地控制冷却剂流动。 Another Bu Xi, the nuclear fission module 30 are separated from each other by one module allows us to control the coolant flow. 控制冷却剂到各个核裂变模块30的流动像基本上按照反应堆堆芯20中的非均匀温度分布引导冷却剂流动那样，有效地管理反应堆堆芯20内的冷却剂流动。 Controlling the flow of coolant to the respective nuclear fission like module 30 substantially in a non-uniform temperature distribution in the reactor core 20 to guide the flow of the coolant as the coolant effectively manage the flow within the reactor core 20. 换句话说，可以将更多的冷却剂引向具有较高温度的那些核裂变模块30，以便提供跨过整个反应堆堆芯20基本上均匀的温度分布。 In other words, the coolant can be directed more nuclear fission module 30 having those higher temperature, so as to provide a substantially across the entire reactor core 20 uniform temperature distribution. 在示范性钠冷却反应堆的情况下，在正常运行期间，冷却剂可以具有近似5. 5m3/s (S卩，近似194ft3/s)的平均额定体流速、和近似2. 3m/s (B卩，近似7. 55ft/s)的平均额定速度。 In the case of an exemplary sodium-cooled reactor, during normal operation, the coolant may have an approximately 5. 5m3 / s (S Jie, approximately 194ft3 / s) the average nominal body velocity, and approximately 2. 3m / s (B Jie approximately 7. 55ft / s) the average nominal speed. 燃料棒50彼此相邻，其间限定燃料棒冷却剂流动通道80 (參见图6)，使冷却剂沿着燃料棒50的外部流动。 The fuel rods 50 adjacent to each other, defining therebetween a coolant flow passage of the fuel rods 80 (see FIG. 6), the coolant flows along the outside of the fuel rods 50. 罐子60可以包括支承燃料棒50和将燃料棒50捆绑在一起的装置(未示出）。 Jar 50 and 60 may comprise means (not shown) of the fuel rods 50 support fuel rods bundled together. 因此，在罐子60内将燃料棒50捆在一起，以便形成前述六边形核裂变模块30。 Accordingly, the fuel rods 60 in the pot 50 bundled together to form the nuclear fission hexagonal module 30. 尽管燃料棒50彼此相邻，但如核动カ反应堆设计领域的普通技术人员所众所周知，燃料棒50仍然被围绕并以盘旋方式沿着每根燃料棒50的长向螺旋状延伸的包装线90 (參见图6)以隔开的关系保持着。 Although the fuel rod 50 adjacent to each other, but if the grades of nuclear reactor design is well known to one of ordinary skill in the art, fuel rods 50 are still around and spirally extends in a spiral manner along the length of the fuel rods 50 of each packaging line 90 (see FIG. 6) to maintain a spaced relationship.
[0064] 參照图3，将多根隔开、纵向延伸和纵向可移动控制棒95 (只示出其中ー些）的每一根都布置在控制棒导管或包壳(未不出）内。 [0064] Referring to FIG 3, a plurality of spaced, longitudinally extending and longitudinally movable control rods 95 (only one of which is shown ー s) of each of the control rod are disposed on a catheter or sheath (not not) within. 控制棒95被对称地布置在所选核裂变模块30内，并沿着预定数量核裂变模块30的长向延伸。 The control rod 95 are symmetrically disposed within the nuclear fission selected module 30, and a predetermined length extending along a number of nuclear fission module 30. 显示成布置在预定数量六边形状核裂变模块30中的控制棒95控制发生在核裂变模块30中的中子裂变反应。 Shown as control rods are arranged in a predetermined number of hexagonally shaped nuclear fission 95 of the control module 30 in the nuclear fission neutron generator module 30 fission reaction. 换句话说，控制棒95包含具有可接受大中子吸收截面的适当中子吸收材料。 In other words, the control rod 95 comprises a sub-acceptable absorption cross section properly sized neutron absorbing material. 关于这方面，吸收材料可以是从基本上由如下组成的群组中选择的金属或准金属：锂、银、铟、镉、硼、钴、铪、镝、钆、钐、餌、铕及其混合物。 In this regard, the absorbent material may be selected from the group consisting essentially of a metal or metalloid: lithium, silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, bait, europium and mixture. 可替代的是，吸收材料可以是从基本上由如下组成的群组中选择的化合物或合金：银铟镉合金、碳化硼、ニ硼化锆、ニ硼化钛、ニ硼化铪、钛酸钆、钛酸镝及其混合物。 Alternatively, the absorbent material may be selected from the group consisting essentially of an alloy or compound of: silver alloy, indium-cadmium, boron carbide, Ni zirconium boride, titanium boride Ni, Ni boride, hafnium titanate, gadolinium, dysprosium titanate and mixtures thereof. 控制棒95可控制地向反应堆堆芯20提供负反应。 Rods 95 may be controlled to provide negative feedback to the reactor core 20. 因此，控制面板95向反应堆堆芯20提供反应管理能力。 Thus, the control panel 95 to provide management capabilities to the reaction reactor core 20. 换句话说，控制棒95能够控制跨过核反应堆堆芯20的中子通量曲线，因此影响核反应堆堆芯20内的温度。 In other words, the control rod 95 can be controlled neutron flux profile across the reactor core 20, and thus affect the temperature in the nuclear reactor core 20.
[0065] 尤其參考图2，3和4，每根燃料棒50含有首尾相接堆叠在其中的多个核燃料芯块100，核燃料芯块100被燃料棒包壳材料110密封地围住。 [0065] Referring particularly to FIGS. 2, 3 and 4, each of the fuel rods 50 which are stacked end to end, comprising a plurality of nuclear fuel pellets 100, nuclear fuel pellets, fuel rod cladding material 100 is sealingly enclose 110. 核燃料芯块100包含像铀-235、铀-233或钚-239那样的上述可裂变核素。 100 as nuclear fuel pellets comprising uranium-235, uranium-233 or plutonium-239 as the fissile nuclides. 可替代的是，核燃料芯块100可以包含像钍-232和/或铀-238那样的可转换核素，它们在裂变过程中蜕变成上文刚提到的可裂变核素。 Alternatively, the nuclear fuel pellet 100 may comprise thorium-232 and / or uranium-238 isotope as above can be converted, they transformed into fissile nuclides just mentioned above in the fission process. 这样的可转换核素材料可以存放在布置在专门指定増殖燃料模块115中的増殖棒中。 Such a material may be stored in the conversion of radionuclide disposed in a specially designated zo proliferation module 115 zo fuel rod proliferation. 如快中子増殖反应堆设计领域的普通技术人员所众所周知，这样的増殖燃料模块115可以被安排成围绕核裂变反应堆堆芯20的内围的“増殖毯”，以便増殖核燃料。 The fast reactor design zo proliferation of ordinary skill in the art is well known, such a proliferation zo fuel module 115 may be arranged to "zo colonization blanket" surrounding the nuclear fission reactor core within the enclosure 20 so zo nuclear proliferation. 进ー步可替代的是，核燃料芯块100可以包含可裂变核素和可转换核素的预定混合物。 Alternatively ー step forward that the nuclear fuel pellets 100 may comprise a predetermined mixture of fissile nuclides and convertible nuclides.
[0066] 參照图4，只举例而非限制性地，核燃料芯块100可以由从基本上由如下组成的群组中选择的氧化物制成：一氧化铀（U0)、ニ氧化铀（U02)、ニ氧化钍（ThO2)(也称为氧化钍)、三氧化铀（UO3),氧化铀-氧化钚（UO-PuO)、八氧化三铀（U3O8)及其混合物。 [0066] Referring to FIG. 4, for example only and not limitation, nuclear fuel pellet 100 may be made selected from the group consisting essentially of oxides of: a uranium oxide (U0), Ni uranium oxide (U02 ), ni thorium oxide (ThO2) (also referred to as thorium oxide), uranium trioxide (of UO3), uranium oxide - plutonium oxide (UO-PuO), uRANIUM (of U3O8) and mixtures thereof. 可替代的是，核燃料芯块100可以主要包含与像(但不限干）锆或钍金属那样的其它金属合金或非合金的铀。 Alternatively, the nuclear fuel pellets of uranium 100 and the image may comprise primarily (but not dry) such as zirconium or thorium metal alloys or other metal alloys. 作为又ー种替代，核燃料芯块100可以主要包含铀的碳化物（UCx)或钍的碳化物、(ThCx)0例如，核燃料芯块100可以由从基本上由如下组成的群组中选择的碳化物制成：一碳化铀（UC)、ニ碳化铀（UC2)、三碳化ニ铀（U2C3)、ニ碳化钍（ThC2)、碳化钍（ThC)及其混合物。 As yet another alternative ー species, nuclear fuel pellet 100 may primarily comprise uranium carbide (UCX) or thorium carbide, (ThCx) 0 For example, nuclear fuel pellet 100 may be selected from the group consisting essentially of the following composition carbides formed: a uranium carbide (UC), Ni uranium carbide (UC2), three Ni uranium carbide (U2C3), Ni thorium (ThC2), thorium (ThC), and mixtures thereof. 作为另ー个非限制性例子，核燃料芯块100可以由从基本上由如下组成的群组中选择的氮化物制成：氮化铀（U3N2)、氮化铀-氮化锆（U3N2Zr3N4X氮化铀钚（（U-Pu) N)、氮化钍(ThN)Jft -锆合金（UZr)及其混合物。密封地围住成堆核燃料芯块100的燃料棒包壳材料110可以是已知抗腐蚀和抗破裂的像ZIRC0L0Y™ (西屋电气公司（Westinghouse ElectricCorporation)的注册■商标）那样的适当错合金。包壳材料110也可以由像铁素体马氏体钢那样的其它材料制成。ー As another non-limiting example, the nuclear fuel pellets 100 may be made selected from the group consisting essentially of a nitride of: uranium nitride (U3N2), uranium nitride - zirconium nitride (U3N2Zr3N4X nitride uranium and plutonium ((U-Pu) N), thorium nitride (ThN) Jft -. zirconium alloy (UZr) was sealed and encloses a stack of nuclear fuel pellets fuel rod cladding material 110 may be a known anti-100 corrosion and cracking as ZIRC0L0Y ™ (Westinghouse electric Corporation (Westinghouse ElectricCorporation) ■ a registered trademark) as the appropriate error alloy cladding material 110 may also be made of other materials such as iron and steel such as ferritic martensitic.
[0067] 返回到图1，反应堆堆芯20被布置在地下室或反应堆压力容器120内，以防止放射性粒子、气体或液体从反应堆堆芯20泄漏到周围生物界。 [0067] Returning to Figure 1, the reactor core 20 is disposed in the basement or the reactor pressure vessel 120, to prevent radioactive particles, gas or liquid leakage from the reactor core 20 to the surrounding biosphere. 由于上文提供的原因，具有内壁表面122的压カ容器120基本上充满像液态钠那样的ー池液体或冷却剂125，达到核裂变反应堆堆芯20浸没在该池冷却剂中的程度。 Reasons provided above, having a degree of nuclear fission reactor core 20 submerged in the coolant pool surface in the inner wall 122 of the pressure container 120 is substantially filled grades as liquid sodium or a pool of liquid such as coolant ー 125, is achieved. 压カ容器120可以是适当大小和厚度的钢、混凝土或其他材料，以减小这样辐射泄漏的风险和支持所需压カ负荷。 Ka pressure container 120 may be a suitable size and thickness of steel, concrete or other materials, to reduce the required pressing load ka risk of such radiation leakage and support. 另外，可能存在密封地围住核裂变反应堆系统10的ー些部分的安全壳(未不出），以加强防止放射性粒子、气体或液体从反应堆堆芯20泄漏到周围生物界的保证。 Further, there may be sealingly enclose a nuclear fission reactor system ー those portions of the containment vessel (not not) 10 to strengthen prevent radioactive particles, gas or liquid leakage from the reactor core 20 to ensure that the surrounding biosphere.
[0068] 再次參照图1，一次环路冷却管130与核裂变反应堆堆芯20耦合，使适当冷却剂可以沿着方向箭头135流过反应堆堆芯20，以便冷却核裂变反应堆堆芯20。 [0068] Referring again to Figure 1, a cooling tube loop 130 is coupled with the nuclear fission reactor core 20, so that a suitable coolant can flow through the reactor core 20 in the direction of arrow 135, so as to cool the nuclear fission reactor core 20. 一次环路冷却管130可以由像不锈钢那样的任何适当材料制成。 A cooling tube loop 130 may be made of any suitable material such as stainless steel. 应该懂得，如果需要的话，一次环路冷却管130不仅可以由铁合金制成，而且可以有色金属合金、锆基合金或其它适当结构材料或复合物制成。 It should be understood, if desired, a cooling tube loop 130 may be made of not only the iron alloy but also non-ferrous metal alloys, zirconium-based alloys, or other suitable structural material or composite. 一次环路冷却管130传送的冷却剂可以是从基本上由如下组成的群组中选择的液态金属：钠、钾、锂、铅及其混合物。 A cooling tube loop 130 may be transmitted by a coolant selected from the group consisting essentially of the liquid metal: sodium, potassium, lithium, lead, and mixtures thereof. 另ー方面，冷却剂可以是像铅-铋（Pb-Bi)那样的金属合金。ー another aspect, the coolant may be as lead - bismuth metal alloy (Pb-Bi) such as. 可替代的是，在本文设想的示范性实施例中，冷却剂是液态钠（Na)金属或像钠-钾(Na-K)那样的钠金属混合物。 Alternatively, in the exemplary embodiment herein contemplated embodiment, the cooling agent is a liquid sodium (Na) as a sodium or a metal - such as a mixture of metallic sodium and potassium (Na-K). 取决于特定反应堆堆芯设计和运行历史，钠冷却反应堆堆芯的正常运行温度可能相对较高。 Depending upon the particular design and operating history of the reactor core, the reactor core is cooled sodium normal operating temperature may be relatively high. 例如，在含有混合铀钚氧化物燃料的500到1，500兆瓦钠冷却反应堆的情况下，在正常运行期间反应堆堆芯出口温度可以从近似510° C(S卩，950° F)到近似550° C (B卩，1，020° F)。 For example, in the case of a sodium-cooled 500 to 1,500 MW containing uranium and plutonium mixed oxide fuel in the reactor, during normal operation of the reactor core outlet temperature from approximately 510 ° C (S Jie, 950 ° F) to approximately 550 ° C (B Jie, 1,020 ° F). 另ー方面，在LOCA (冷却剂丧失事故)或LOFTA (流量短暂丧失事故)期间，取决于反应堆堆芯设计和运行历史，燃料包壳峰温度可能达到近似600° C(BP, I, 110° F)或更高。 Another aspect ー, during the LOCA (loss of coolant accident) or LOFTA (transient loss of flow accident), depending on design and operating history of the reactor core, fuel cladding peak temperature may reach approximately 600 ° C (BP, I, 110 ° F) or higher. 此外，在LOCA后和LOFTA后情形期间以及在反应堆暂停运行期间的衰变热积累可能造成不可接受的热积聚。 In addition, in the case of post-LOCA and heat as well as during the decay heat accumulated during reactor out of operation may cause unacceptable after LOFTA accumulation. 因此，在一些情况下，在正常运行情形和事故后情形两者期间移除核裂变反应堆堆芯20产生的热量是合适的。 Thus, in some cases, in the case of normal operation and accident remove heat generating nuclear fission reactor core 20 is suitable both during scenario.
[0069] 仍然參照图1，核裂变反应堆堆芯20生成的带热冷却剂沿着冷却剂流线或流径140流到也浸没在冷却剂池120中的中间热交換器150。 [0069] Still referring to Figure 1, the nuclear fission reactor core 20 generates heat with the coolant flow 140 also immersed in the coolant tank 120 along the coolant flow line or flow path 150 of the intermediate heat exchanger. 中间热交換器150可以由像适当不锈钢那样，耐冷却剂池125中的钠冷却剂的热效应和腐蚀效应的任何方便材料制成。 The intermediate heat exchanger 150 may be made as appropriate such as stainless steel, heat-resistant material of any convenient effects and corrosion effects of sodium coolant in the coolant tank 125 is made. 如下文更全面所述，沿着冷却剂流径140流动的冷却剂流过中间热交換器150，并继续流过ー次环路冷却管130。 As described more fully below, flows along the coolant flow path 140 of the coolant flows through the intermediate heat exchanger 150, and continues to flow through the secondary loop cooling tube 130 ー. 应该懂得，如下文更全面公开，由于发生在中间热交換器1510中的热传递，离开中间热交換器150的冷却剂已经冷却了。 It should be understood, as more fully disclosed, since heat transfer occurs in the intermediate heat exchanger 1510, leaving the intermediate heat exchanger 150 to the coolant has cooled. 可以是机电泵的第一泵110与一次环路冷却管130耦合，并与一次环路冷却管130传送的反应堆冷却剂流体连通，以便通过一次环路冷却管130，通过反应堆堆芯20，沿着却剂流径140将反应堆冷却剂抽运到中间热交換器150。 May be an electromechanical pump the first pump 110 and a condenser coupled to the loop 130, and fluid communication with the primary reactor coolant loop transfer cooling tube 130, so that a loop through the cooling tube 130, through the reactor core 20, along a coolant flow path 140 to the reactor coolant is pumped into the intermediate heat exchanger 150.
[0070] 再次參照图1，配备从中间热交換器150中去热的二次环路管道180。 [0070] Referring again to Figure 1, with the intermediate heat exchanger 150 to heat the secondary circulation conduit 180. 二次环路管道180包含二次“热”支路管段190和二次“冷”支路管段200。 Secondary loop 180 comprises secondary conduit "hot" branch pipe 190 and the secondary "cold" branch pipe 200. 二次热支路管段190和二次冷支路管段200整体与中间热交換器150连接。 Secondary thermal bypass pipe sections 190 and 200 integral with the second intermediate heat exchanger 150 connected to the cold leg pipe. 包括热支路管段190和冷支路管段200的二次环路管道180包含像从基本上由如下组成的群组中选择的液态金属那样的流体：钠、钾、锂、铅及其混合物。 Heat pipe 190 includes a bypass conduit 180 and the secondary loop cold leg pipe 200 as a liquid containing a metal selected from the group consisting essentially of the fluid as: sodium, potassium, lithium, lead, and mixtures thereof. 另ー方面，该流体可以是像铅-铋（Pb-Bi)那样的金属合金。ー another aspect, the fluid may be as lead - bismuth metal alloy (Pb-Bi) such as. 可替代的是，在本文设想的示范性实施例中，该流体适当地可以是液态钠（Na)金属或像钠-钾(Na-K)那样的钠金属混合物。 Alternatively, in the exemplary embodiment herein contemplated embodiment, the fluid may suitably be a liquid sodium (Na) as a sodium or a metal - such as a mixture of metallic sodium and potassium (Na-K). 由于刚才所述的原因，二次热支路管段190从中间热交換器150延伸到蒸汽发生器和过热器组合体210(下文称为“蒸汽发生器210”)。 The reasons just described, the secondary heat bypass pipe 190 extends from the intermediate heat exchanger 150 to the steam generator and superheater assembly 210 (hereinafter referred to as "steam generator 210"). 关于这方面，在通过蒸汽发生器210之后，由于发生在蒸汽发生器210内的热传递，流过二次环路管道180和离开蒸汽发生器210的冷却剂处在比进入蒸汽发生器210之前低的温度和焓上。 In this regard, after passing through the steam generator 210, since heat transfer occurs in the steam generator 210 flows through the conduit 180 and the secondary loop coolant exits the steam generator 210 into the steam generator than in the previous 210 the low temperature and enthalpy. 在通过蒸汽发生器210之后，沿着延伸到提供上述热传递的中间热交換器150的的“冷”支路管段200，像通过可以是机电泵的第二泵220那样抽运冷却剤。 After passing through the steam generator 210, extending along the heat transfer to the provision of the intermediate heat exchanger "cold" section 150 of the bypass tube 200, as by a second pump may be a pump 220 as electromechanical pumping cooling Ji. 下文将马上一般地描述蒸汽发生器210生成蒸汽的方式。 Hereinafter will now be described in general embodiment of the steam generator 210 generates steam.
[0071] 还再次參照图1，处在蒸汽发生器210中的是具有预定温度和压强的水体230。 [0071] Referring also again to Figure 1, in the steam generator 210 is water having a predetermined temperature and pressure of 230. 流过二次热支路管段190的流体通过传导将它的热量传递给处在比流过二次热支路管段190的流体低的温度上的水体230。 A secondary fluid flowing through the bypass pipe 190 heat conduction by transferring its heat to the water in the body 230 than on the low temperature of the fluid flowing through the secondary heat pipe 190 branches. 随着流过二次热支路管段190的流体将它的热量传递给水体230，一部分水体230将按照蒸汽发生器210内的预定温度和压强蒸发成蒸汽240。 As the fluid flows through the secondary heat pipe 190 to bypass its heat transferred to the water 230, the portion of the water 230 in accordance with a predetermined temperature and pressure within the steam generator 210 to the evaporator 240 steam. 然后，蒸汽240通过蒸汽管250行进,蒸汽管250的一端与蒸汽240蒸气连通,而另一端与水体230液体连通。 Then, steam 240 travels through the steam pipe 250, one end 250 of the steam pipe with steam vapor communication 240, 230 and the other end in fluid communication with the water body. 旋转涡轮机260与蒸汽管250耦合，以便涡轮机260随着蒸汽240从中通过而旋转。 Rotating turbine 260 and the steam tube 250 is coupled to the turbine 260 with steam 240 is rotated by therethrough. 像通过旋转涡轮机轴280那样与涡轮机260耦合的发电机270随着涡轮机180旋转而发电。 Like the turbine 260 and 280 as a generator 270 coupled with the power generating turbine 180 is rotated by the rotation of the turbine shaft. 另外，冷凝器290与蒸汽管250耦合，接收通过涡轮机260的蒸汽。 Further, the condenser 290 is coupled to steam pipe 250, receives steam through the turbine 260. 冷凝器290使蒸汽凝结成液态水，并且将任何废热传递给像冷却塔300那样，与冷凝器29相联系的散热器。 A condenser 290 so that steam is condensed into liquid water, and pass any waste heat to the cooling tower 300 as the image, the radiator 29 associated with the condenser. 通过插在冷凝器290与蒸汽发生器210之间、可以是机电泵的第三泵3130将冷凝器290凝结的液态水沿着蒸汽管250从冷凝器290抽运到蒸汽发生器210。 By interpolating between the condenser 290 and the steam generator 210, it may be a third electromechanical pump 3130 pump condenser 290 along the vapor condensed liquid pumping pipe 250 from the condenser 290 to the steam generator 210.
[0072] 如从图5中最佳看出，取代前述的六边形状配置，可以将核裂变模块30安排成限定统称为222的平行六面体状核裂变反应堆堆芯配置。 [0072] As best seen from Figure 5, instead of the hexagonal-shaped configuration, the module 30 may be arranged to nuclear fission collectively define 222 parallel hexahedron-shaped nuclear fission reactor core configuration. 关于这方面，由于下文提供的原因，核裂变反应堆堆芯222的反应堆堆芯外壳40限定第一端330和第二端340。 In this regard, due to the reasons provided below, the nuclear fission reactor core of the reactor core 222 of the housing 40 defines a first end 330 and a second end 340. [0073] 再次參照图5，与为核裂变反应堆堆芯选择的配置无关，核裂变反应堆堆芯20或222可以配置为行波核裂变反应堆堆芯。 [0073] Referring again to FIG. 5, irrespective of the configuration selected for the nuclear fission reactor core of the nuclear fission reactor core 20 or 222 may be configured as a traveling wave nuclear fission reactor core. 关于这方面，可以包括像(但不限干)U-233、U-235或Pu-239那样的可裂变核材料的浓缩同位素的相对较小和可拆除核裂变点火器350可以适当地处在反应堆堆芯222中。 In this regard, the image may include (but not dry) U-233, U-235 fissile nuclear material or as enriched isotopes of Pu-239 is relatively small and can be removed nuclear fission igniter 350 may be suitably located in reactor core 222. 只举例而非限制性地，点火器350可以处在与反应堆堆芯340的第二端340相対的第一端330附近。 By way of example only and not limitation, the igniter 350 may be located near the first end 330 and a second end of the reactor core of Dui phase of 340,340. 点火器350释放出中子。 Igniter 350 to release neutrons. 点火器350释放的中子被核裂变模块30中的可裂变和/或可转换材料捕获，引发链式裂变反应。 Igniter 350 is released by nuclear fission neutrons module 30 of fissionable and / or fertile material captures initiate fission chain reaction. 如果需要的话，一旦链式反应变成自持的，就可以拆除点火器350。 If necessary, once the chain reaction becomes self-sustaining, it can dismantle the igniter 350.
[0074] 仍然參照图5，点火器350引发三维行进爆燃波或“燃烧波”360。 [0074] Still referring to FIG. 5, the igniter 350 triggered traveling deflagration wave or a three-dimensional "combustion wave" 360. 当点火器350生成中子引起“点火”时，燃烧波360从第一端330附近的点火器330到反应堆堆芯220的第ニ端340向外行迸，以便形成行进或传播燃烧波360。 When the igniter 350 generates neutrons, "fire", the combustion wave 360 ​​near the first end 330 from the igniter 330 to the reactor core 220 of end 340 outwardly ni Beng row, or so as to form the traveling wave 360 ​​propagation combustion. 换句话说，每个核裂变模块30都能够随着燃烧波360传过反应堆堆芯222而接收至少一部分燃烧行波360。 In other words, each module 30 can nuclear fission reactor core 360 ​​222 As the combustion wave propagating through the wave receiving at least a portion of the combustion line 360. 燃烧行波360的速度可以是恒定的或不恒定的。 Combustion speed traveling wave 360 ​​may be constant or not constant. 因此，可以控制燃烧波360传播的整数。 Thus, it is possible to control the propagation of the combustion wave 360 ​​integer. 例如，以预定或编程方式纵向移动前述控制棒95 (參见图3)可以向下驱动或降低布置在核裂变模块30中的燃料棒50的中子反应性。 For example, a predetermined program or the control rod 95 moves longitudinally (see FIG. 3) may be driven or reduced fuel rods disposed in the neutronic reactivity of nuclear fission module 30 50 downwardly. 这样，相对于燃烧波360前面的“未燃烧”核燃料50的中子反应性，向下驱动或降低处在燃烧波360的地点上当前正在燃烧的核燃料50的中子反应性。 Thus, with respect to the neutronic reactivity of the combustion wave front 360 "unburned" fuel 50, driven downward in the combustion wave or reducing the neutronic reactivity of the current location 360 burning fuel 50. 这种结果给出了方向箭头365所指的燃烧波传播方向。 This result shows the direction of propagation of the combustion wave within the meaning of the direction of arrow 365. 以这种方式控制反应性使受到反应堆堆芯220的运行约束的燃烧波360的传播速率达到最大。 In this manner control the reactivity so that the reactor core 220 by operating constraint propagation speed of the combustion wave 360 ​​reaches the maximum. 例如，使燃烧波360的传播速率达到最大提供了将燃耗控制在传播所需的最小值之上和部分通过反应堆堆芯结构材料的中子注量限制设置的最大值之下的手段。 For example, the combustion wave propagation rate reaches the maximum 360 provides a means below the maximum value on the minimum burnup required for controlling the spread and the amount of the core part of the neutron through the reactor structural material injection set limit.
[0075] 这样行波核裂变反应堆的基本原理详细公开在2006年11月28日以RoderickA. Hyde等人的名字提交和发明名称为“Automated Nuclear Power Reactor For Long-TermOperation (长期运行的自动核动カ反应堆)”的待审美国专利申请第11/605,943号中，该申请已转让给本申请的受让人,特此通过弓I用将其整个公开文本并入本文中。 [0075] Such lines rationale wave nuclear fission reactor detailed disclosure submitted in RoderickA. Hyde et al name in 2006 November 28 and entitled "Automated Nuclear Power Reactor For Long-TermOperation (long-running auto-nuclear movement reactor ka) "in copending U.S. Patent application No. 11 / 605,943, which application is assigned to the assignee of this application, hereby incorporated by I bow with its entire disclosure is incorporated herein.
[0076] 參照图6，所示的是直立相邻六边形状核裂变模块30。 [0076] Referring to FIG 6, a hexagonal-shaped nuclear fission module 30 shown adjacent to the upright. 虽然只示出了三个相邻核裂变模块30，但应该明白，在反应堆堆芯20中存在大量核裂变模块30。 Although only three adjacent nuclear fission module 30, it should be understood that the presence of a large number of modules 30 in the nuclear fission reactor core 20. 每个核裂变模块30被安装在水平延伸反应堆堆芯下支承板370上。 Each nuclear fission module 30 is mounted on a horizontally extending support plate 370 of the reactor core. 反应堆堆芯下支承板370跨过所有核裂变模块30的底端部地适当延伸。 Lower reactor core support plate 370 across all modules nuclear fission bottom end portion 30 extending appropriate manner. 由于下文提供的原因，反应堆堆芯下支承板370含有从中通过的埋头孔380。 For reasons provided below, the reactor core support plate 370 comprising a countersink 380 therethrough. 埋头孔380具有允许冷却剂流入的开ロ端390。 Countersink 380 allows the coolant flows having open ends 390 ro. 跨过所有核裂变模块30的顶端部或排放部分水平延伸和可拆除地与核裂变模块30连接的是盖住所有核裂变模块30的反应堆堆芯上支承板400。 All modules across the top portion of nuclear fission or discharge portion 30 extending horizontally and detachably connected with the nuclear fission module 30 is a support plate 400 to cover all the nuclear fission reactor core modules 30. 反应堆堆芯上支承板400还限定允许冷却剂从中流过的多个流槽410。 The reactor core support plate 400 also defines a coolant allowed to flow therethrough a plurality of flow grooves 410. 一次环路管道130和第一泵170 (參见图I)沿着方向箭头140所指的冷却剂流径或流线将反应堆冷却剂输送到核裂变模块30。 A circulation conduit 130 and the first pump 170 (see FIG. I) will be delivered to the reactor coolant nuclear fission module 30 along the coolant flow path or flow direction arrow 140 is pointing. 然后一次冷却剂继续沿着冷却剂流径140流动，并通过在下支承板370中形成的开ロ端390。 Then continue along the primary coolant flow of the coolant flow path 140, and the open end formed by ro lower support plate 370 390.
[0077] 如前所述，与为反应堆堆芯20选择的配置无关，重要的是移动反应堆堆芯20和其中的核裂变模块30产生的热量。 [0077] As described above, irrespective of the configuration selected for the reactor core 20, it is important to heat the reactor core 20 and moving the nuclear fission module 30 which generated. 由于几方面原因，适当的去热很重要。 Due to several reasons, proper heat removal is important. 例如，如果峰温度超过材料极限，则可能对反应堆堆芯结构材料造成热损伤。 For example, if the peak temperature exceeds the material limit, it may cause thermal damage to the reactor core structural materials. 这样的峰温度可能因改变了结构的机械性质，尤其与热蠕变有关的那些性质而非所希望地缩短了经受这样峰温度的结构的运行寿命。 Such changes may be due to the peak temperature of the mechanical properties of the structure, particularly those associated with thermal creep properties, rather than the desired operating life shortened peak temperature subjected to such a configuration. 此外，反应堆功率密度受堆芯结构材料不受损伤地承受高峰温度的能力限制。 In addition, the power density of the reactor core structural material is not subject to capacity limitations damaging temperature peaks. 另外，核裂变反应堆10可替代地可以用于进行像确定温度对反应堆材料的影响的测试那样的测试。 In addition, nuclear fission reactor 10 may alternatively be used to determine the effect of temperature on the reactor as the material of the test as a test. 通过适当地从反应堆堆芯中去热控制反应堆堆芯温度对于成功进行这样的测试是重要的。 By appropriately heat from the reactor core to control the temperature of the reactor core for a successful test was carried out it is important.
[0078] 此外，可能希望传热流体通过中间热交換器150的流速达到均匀。 [0078] In addition, it may be desirable to achieve a uniform heat transfer fluid flow rate through the intermediate heat exchanger 150. 这样的均匀流速另外可以避免到核裂变反应堆堆芯的不均匀冷却剂流动和导致堆芯反应性扰动。 Such uniform velocity unevenness additional coolant flow to avoid nuclear fission reactor core and core reactivity results in disturbances. 并且，可能希望提供冷却剂流过热交換器的均匀分布，以避免冷却剂通过热交換器的偏向流动。 And, it may be desirable to provide uniform distribution of coolant flow through the heat exchanger, in order to avoid bias flow of coolant through the heat exchanger. 避免冷却剂的偏向流动可以缓解热交換器中的定域温度“热点”的发展。 Avoid bias flow of coolant can ease the development of "hot spots" in the localized temperature of the heat exchanger. 这样的定域温度“热点”另外可能缩短热交換器的运行寿命。 Such localized temperature "hot spots" may further shorten the operating life of the heat exchanger. 均匀流也起跨过热交換器的传热表面均匀加强热交换，从而加强给定热交换区域的热交换的作用。 Uniform flow across the heat transfer surface of the heat exchanger also as uniformly strengthen the heat exchange, thereby enhancing heat exchange given heat exchange zone. 中间热交換器150的结构和运行解决了这些担心。 The structure and operation of the intermediate heat exchanger 150 to address those concerns.
[0079] 现在描述中间热交換器150的结构。 [0079] Now to describe the structure of the intermediate heat exchanger 150. 參照图I，7，8，8A和9，中间热交換器150包含附在压力容器120的内壁表面122上的热交換器主体420，以便将中间热交換器150支承在压カ容器120内。 Referring to FIG I, 7,8,8A and 9, attached to the intermediate heat exchanger comprising a heat exchanger body 150 on the inner wall surface of the pressure vessel 120 122 420 to the intermediate heat exchanger 150 is supported in the container 120 ka pressure. 作为ー种替代品，限定池125的内壁表面122可以形成中间热交換器150的后壁。 As ー alternative species, cell 125 defines an inner wall surface 122 may be formed in the rear wall of the intermediate heat exchanger 150. 热交換器主体420包含将一次流体排放容腔或排放空腔室430限定在其中的直立大致L形(横截面）后部425。 The heat exchanger 420 comprises a body cavity fluid discharge chamber or discharge chamber 430 defined therein upstanding substantially L-shaped (cross section) of the rear portion 425. 如下文更详细所述，一次流体排放空腔室430被做成通过一次流体排放空腔室430提供第一传热流体（即，一次传热流体）的均匀流的形状。 As described in greater detail below, the primary fluid discharge chamber cavity 430 is made by providing a fluid discharge shape of the hollow chamber of uniform flow of the first heat transfer fluid (i.e., a heat transfer fluid) 430. 通过热交換器主体420的后部425形成，但在一次流体排放空腔室430内的是通向一次环路冷却管130的一次流体排放ロ435。 420 formed by a rear portion of the heat exchanger body 425, but during a fluid discharge chamber cavity 430 is a cooling tube loop 130 leading to a primary fluid discharge ro 435. 与后部425连接的是为热二次钠限定底空腔450的热交换器主体420的底部440。 Connected to the rear portion 425 of the bottom 420 of the body 450 defining the bottom of the cavity of the heat exchanger 440 to heat the secondary sodium. 具有底空腔排放侧或排放ロ455的底空腔450形成盒状结构，该盒状结构上面具有像通过焊接那样，将多个直立板状传热构件470连成整体的顶表面460。 A cavity having a bottom end of the discharge side or discharge ro cavity 455 formed in a box-like structure 450, having the above structure as the cartridge as by welding, a plurality of upright plate-shaped heat transfer member 470 is integrally attached to the top surface 460. 每个传热构件470限定在流动通道460的各端上具有入口490和出ロ500的从中通过的流动通道480。 Each heat transfer member 470 defines a flow passage therethrough having an inlet 490 and outlet 500 ro 480 on each end of the flow channel 460. 入口490与流过冷支路管段200的传热流体流体连通。 Inlet 490 in fluid communication with the heat transfer fluid flowing through the cold leg pipe 200 and. 出ロ500与底空腔450中的传热流体流体连通。 Ro fluid communication with the heat transfer fluid 500 of the cavity 450 in the bottom. 此外，应该懂得，不使用导管或歧管地将一次流体供应给热交換器主体420。 Further, it is appreciated that without the use of conduits or the manifold to the primary fluid supplied to the heat exchanger body 420. 换句话说,无导管或无歧管地将一次流体供应给热交換器主体420。 In other words, no non-manifold conduit or to the primary fluid supplied to the heat exchanger body 420. 另外,应该懂得，中间热交換器150的舱入口侧可以无歧管，并且中间热交換器150的出ロ侧也可以无歧管。 Further, it should be appreciated that the inlet side of the intermediate heat exchanger tank 150 may be non-manifold and an intermediate heat exchanger 150 may ro no side manifold. 因为不需要这样的导管或歧管，所以可以降低构建反应堆10的投资成本和/或热交换器150的制造成本。 Since no such duct or manifold, it is possible to reduce the investment cost of the reactor 10 constructed and manufacturing cost / or heat exchanger 150.
[0080] 參照图8，8A和9，中间热交換器150包含多个相邻传热构件470。 [0080] Referring to FIGS. 8,8A and 9, the intermediate heat exchanger 150 comprises a plurality of adjacent heat transfer member 470. 多个相邻传热构件470被隔开相对较小预定距离“d”，预定距离“d”限定相邻传热构件470之间的多条流动通路510。 A plurality of adjacent heat transfer members 470 are spaced apart a predetermined relatively small distance "d", the predetermined distance "d" defining a plurality of flow path 510 between adjacent heat transfer member 470. 距离“d”是在流动通路510之间实现均匀流动分布所需的那个距离。 Distance "d" is the distance to achieve the desired uniform flow distribution between the flow passage 510. 换句话说，将传热构件470隔开距离“d”，以便使一次传热流体均匀分散流过多条流动通路510。 In other words, the heat transfer member 470 separated by a distance "d", so that a uniform dispersion of the heat transfer fluid flow path 510 of flow excess. 如果需要的话，可以将相邻传播构件470之间的距离“d”设计成对于不同反应堆堆芯配置具有不同值，以便使一次传热流体通过多条流动通路的流动达到均匀分布。 If desired, the propagation member may be a distance between the adjacent 470 "d" is designed to have different values ​​for the different configuration of the reactor core, the primary heat transfer fluid in order to achieve uniform distribution of flow through the plurality of flow paths. 这样做是因为特定反应堆堆芯配置可能具有随着传热流体向热交換器150行进而改变或干扰一次传播流体的自由流动的堆芯内结构。 This is done because a particular reactor core having an inner configuration may vary as a heat transfer fluid to the heat exchanger 150 or interfere with the travel time spread of the free flow of fluid in the core structure. 可以将距离“d”设计成具有不同值，以便补偿这种影响。 Distance "d" may be designed to have different values, in order to compensate for this effect. 在另ー个实施例中，热交換器主体420可以包含将传热流体的流动引向热交換器150的引导结构515。ー In another embodiment, the heat exchanger body 420 may comprise a heat transfer fluid flowing toward the heat exchanger 150 of the guide structure 515. 引导结构515适当地跨过传热构件470并与流动通路510相联系，以便将传热流体引导到流动通路510中。 Suitably the guide structure 515 and across heat transfer member 470 associated with the flow passage 510, so that the heat transfer fluid to the flow passage 510. 热交換器主体420进ー步包含密封地安装在后部425的上部和多个传热构件470的上部上或与它们连接的顶部520。 The heat exchanger further comprises a main body 420 into ー sealingly mounted on the upper rear portion of the upper portion 425 and a plurality of heat transfer members 470 or 520 of the top they are attached. 顶部520将从蒸汽发生器210接收沿着流径532流动的冷却二次钠的顶空腔530限定在其中。 520 from the top of the steam generator 210 receives the top along the cooling cavity sodium secondary flow path 532 flow 530 defined therein. 沿着流径532流动的冷却二次钠和沿着流径140流动的一次传热流体限定交叉流动配置。 The sodium secondary flow path along the cooling flow 532 is disposed along and defining a cross-flow of heat transfer fluid flow path 140 flows. 在这种交叉流动配置中，流径532大致与中间热交換器150中的流径140垂直（B卩，±45° )。 In such a cross-flow configuration, flow path 532 substantially in the flow path 150 perpendicular to the intermediate heat exchanger 140 (B Jie, ± 45 °). 顶空腔530与入口490连通，以便使冷却二次钠流过入口490，流入流动通道470中，流过出ロ500并流入底空腔450中。 A top cavity 530 communicates with the inlet 490 to flow through the cooling sodium secondary inlet 490, flows into the flow passage 470, flows through the bottom and into the cavity 500 ro 450.
[0081] 參照图9A和9B，一个可替代实施例的中间热交換器150包含冷却二次传热流体沿着流径532流过的冷支路管段200。 The intermediate heat exchanger [0081] Referring to FIGS. 9A and 9B, an alternative embodiment 150 comprises a secondary cooling heat transfer fluid flowing the flow path 532 along the cold leg pipe 200. 关于这方面，冷却二次传热流体通过开ロ536a进入板件534中，从在板件534中形成的开ロ536b排放。 In this regard, the secondary cooling heat transfer fluid through the opening 536a into the plate 534 ro in ro discharged from the opening 536b formed in the plate member 534. 二次传热流体继续沿着流径532流动，进入返回管段538中，使二次传热流体返回到蒸汽发生器210。 A secondary heat transfer fluid continues to flow along the flow path 532 into the return pipe 538, the secondary heat transfer fluid is returned to the steam generator 210. 沿着流径532流动的冷却ニ次钠和沿着流径140流动的一次传热流体限定相向流动配置。 Ni sodium views along the cooling flow path 532 and a flow of heat transfer fluid flowing along the flow path 140 define opposite flow configuration. 在这种相向流动配置中，流径532与中间热交換器150中的流径140平行但相反。 In such opposite flow configuration, flow path 150 of flow path 532 and the intermediate heat exchanger 140 in parallel but opposite.
[0082] 參照图9C和9D，一个可替代实施例的中间热交換器150包含冷却二次传热流体沿着流径532流过的冷支路管段200。 [0082] Referring to FIGS. 9C and 9D, an alternative embodiment of the intermediate heat exchanger 150 comprises a secondary cooling heat transfer fluid flowing the flow path 532 along the cold leg pipe 200. 关于这方面，冷却二次传热流体通过开ロ536a进入板件534中，从在板件534中形成的开ロ536b排放。 In this regard, the secondary cooling heat transfer fluid through the opening 536a into the plate 534 ro in ro discharged from the opening 536b formed in the plate member 534. 二次传热流体继续沿着流径532流动，进入返回管段538中，使二次传热流体返回到蒸汽发生器210。 A secondary heat transfer fluid continues to flow along the flow path 532 into the return pipe 538, the secondary heat transfer fluid is returned to the steam generator 210. 沿着流径532流动的冷却ニ次传热流体和沿着流径140流动的一次传热流体限定同向流动配置。 Ni flowing along the cooling flow path 532 and the secondary heat transfer fluid arranged to define with the heat transfer fluid flows along the primary flow path 140 flows. 在这种同向流动配置中，流径532与中间热交換器150中的流径140平行且方向相同。 Co-flow configuration, flow path 150 of flow path 532 and the intermediate heat exchanger 140 in the same direction and parallel to this.
[0083] 參照图10，11，12和13，所示的是传热构件470的可替代实施例。 [0083] Referring to FIGS. 10,11, 12 and 13, heat transfer member 470 of the alternative embodiment illustrated. 关于这方面，多个传热构件470的至少ー个包含限定增强的传热表面550的壁540，增强的传热表面550调节一次传热流体沿着增强的传热表面550的流动。 In this regard, at least a plurality of the heat transfer member 470 of the walls 540 ー defined comprising reinforcing heat transfer surfaces 550, 550 to enhance heat transfer surface of the heat transfer fluid along a primary flow regulating enhanced heat transfer surfaces 550. 关于这方面，壁540将较热一次钠（即，第一传热流体)与较冷二次钠（即，第二传热流体)分开。 In this regard, the hot wall 540 Sodium time (i.e., a first heat transfer fluid) and the secondary cooler sodium (i.e., a second heat transfer fluid) separately. 多个传热构件470的至少ー个包含从形成增强的传热表面550的壁540向外延伸的至少ー个整体连接外散热片或外凸缘560。 A plurality of heat transfer members comprise at least one ー 470 is formed from the enhanced heat transfer surface ー least one heat sink or integrally connected to the outer wall of the outer flange 560 extending outwardly 540,550. 外凸缘560通过增加使传热增加的表面积来加强传热。 The outer flange 560 to enhance heat transfer by increasing the heat transfer surface area increases. 可替代的是，多个传热构件470的至少ー个包含从形成增强的传热表面550的壁540向外突出的至少ー个结570。 Alternatively, a plurality of at least one heat transfer member is at least ー ー 570 comprises a knot formed projecting outwardly from the enhanced heat transfer surface of the wall 470 of 540,550. 结570通过増加使传热增加的表面积来加强传热。 570 to strengthen the junction of increase in heat transfer by increasing the heat transfer surface area. 作为另ー种替代品，多个传热构件470的至少ー个包含为了加强传热的目的从壁540向内延伸的至少ー个整体连接内散热片或内凸缘580。 As a further alternative ー species, the plurality of the heat transfer member comprises at least one ー 470 for reinforcing purposes within the at least one heat transfer ー integrally connected to the inner flange 580 or fins extending inwardly from the wall 540. 内凸缘580通过增加使传热增加的表面积来加强传热。 Inner flange 580 by increasing the heat transfer surface area increased to enhance heat transfer. 作为又ー种替代品，多个传热构件470的至少ー个包含沿着流动通道490延伸的至少ー根导管590，用于调节冷却传热流体沿着导管590的流动。 As yet another alternative ー species, the plurality of the heat transfer member comprises at least ー 470 along at least one flow channel 490 extending root ー conduit 590 for regulating the flow of cooled heat transfer fluid along the conduit 590.
[0084] 图13A和13B展不了包括增强的传热表面550的进一步实施例。 [0084] Figures 13A and 13B show a further embodiment not including enhanced heat transfer surfaces 550 of the embodiment. 关于这方面，夕卜凸缘560可以具有随着凸缘560从壁540的前部592延伸到壁540的后部594逐渐增大的传热表面积。 In this regard, flange 560 may have Bu Xi with a flange 560 extending from the front portion 592 of the wall 540 to the rear 594 of the wall 540 is gradually increased heat transfer surface area. 热力学领域的普通技术人员应该懂得，因为一次传热流体从壁540的前部592流到壁540的后部594，所以较靠近壁540的前部592的地方比较靠近壁540的后部594的地方发生更大部分的传热。 Thermodynamics of ordinary skill will appreciate, because of a heat transfer fluid from the front portion 592 of the wall 540 the rear wall 594 flows to 540, where it is relatively close to the wall 540 of the front portion 592 of the rear wall 540 of the closer 594 larger part of the local heat transfer occurs. 因此，在较靠近壁540的前部592的地方发生较多的传热，而在较靠近壁540的后部594的地方发生数量減少的传热。 Thus, more heat transfer takes place closer to the front portion 592 of the wall 540, and a reduced number of heat transfer takes place closer to the rear wall 540 of 594. 为了补偿壁540的后部594附近的减少传热，使凸缘560的传热表面积随着凸缘560从壁540的前部592延伸到壁540的后部594逐渐増大。 To compensate for the reduced heat transfer wall 540 near the rear portion 594, the heat transfer surface area of ​​the flange 560 with a flange 560 extending from the front portion 592 to the rear wall 540 of the wall 540 594 zo gradually large. 例如，可以将凸缘560做成在前部592附近具有较小端部而在后部594附近具有较宽端部的楔形。 For example, the flange 560 can be made close to the front end portion 592 having a small wedge-shaped portion having a wider end portion in the vicinity of the rear portion 594. 作为另ー种替代品，从壁540向外突出的结570的密度（即，単位面积结570的数量)可以从前部592到后部594逐渐增加，以便使传热表面积从壁540的前部592到壁540的后部594逐渐増大。 As a further alternative ー species, projecting outwardly from the wall 540 of the junction 570 density (i.e., the area of ​​the junction. Unit number 570) from the front portion 592 to the rear portion 594 gradually increases, so that the heat transfer surface area from the front portion 540 of the wall rear wall 540 to 594,592 zo gradually large. 结570的这种配置补偿了发生在壁540的后部594附近的传热的減少。 This configuration junction 570 compensates for reduction occurs in the vicinity of the rear wall 540 of the 594 heat transfer.
[0085] 现在转到图14和15，所示的是核裂变反应堆系统10的可替代实施例，其中存在像第一热交换器600和第二热交换器610那样的多个热交換器。 [0085] Turning now to FIGS. 14 and 15, are shown a nuclear fission reactor system of alternative embodiment 10, wherein there is a plurality of heat exchanger 600 as a first image and a second heat exchanger 610. 第一热交换器600和第二热交换器610的姆ー个分别通过将冷传热流体供应给热交換器600/610的第一冷支路管段620a和第二冷支路管段620b与蒸汽发生器210耦合。 A first heat exchanger 600 and the second heat exchanger 610 through the first Farm ー a cold leg pipe section 620a and second section 620b and the cold leg pipe 600/610 of steam heat exchanger is supplied to the cold heat transfer fluid generator 210 is coupled. 另外，第一热交換器600和第二热交換器610的每ー个分别通过使得可以从热交換器600/610中提取加热传热流体的第一热支路管段630a和第二热支路管段620b与蒸汽发生器210耦合。 Further, the first heat exchanger 600 and the second heat exchanger 610 each ー substituents each may be extracted by heat transfer fluid such that the first heat pipe section 630a and a second bypass branch from the heat exchanger in 600/610 620b is coupled with the steam generator tube section 210. 此外，如果需要的话，由于当前所述的原因，可以存在安装在第一冷支路管段620a中的第一截止阀640a、和安装在第ニ冷支路管段620b中的第二截止阀640b。 Further, if desired, because of the current, there may be a first shutoff valve 640a installed in the first pipe 620a in the cold leg and a second shutoff valve 640b is mounted on the cold leg pipe 620b ni in. 另外，由于当前所述的原因，可以存在安装在第一热支路管段630a中的第三截止阀650a、和安装在第二热支路管段630b中的第四截止阀650b。 Further, because of the current, there may be a third shut-off valve 650a is mounted on the first heat pipe section 630a of the branch, and a fourth shut-off valve 650b is mounted in the second heat pipe section 630b of the branch. 关于这方面，如果需要的话，可以关闭截止阀640a/650a以阻断去往和来自第一热交 In this regard, if desired, you can close the valve 640a / 650a to heat the first block to and from the post
换器600的冷却剂流，从而隔离第一热交換器600。 Coolant flow transducer 600, thereby isolating the first heat exchanger 600. 此外，如果需要的话，可以关闭截止阀640b/650b以阻断去往和来自第二热交換器610的冷却剂流，从而隔离第二热交換器610。 Further, if desired, can be closed off valve 640b / 650b to block the second heat exchanger to and from the coolant flow 610, to isolate the second heat exchanger 610. 如果在任何传热构件470的壁540中发生泄漏，则可能希望隔离第一热交換器600或第二热交換器610。 If any leakage occurs at the wall 540 of the heat transfer member 470, the heat exchanger may be desirable to isolate the first 600 or the second heat exchanger 610. 另外，将像泵660a和660b那样的多个泵与多个热交換器600和610的各自ー个耦合，以便将冷却传热流体从热交換器600和610抽运到核裂变反应堆堆芯20。 Further, the plurality of pumps as pumps 660a and 660b and a plurality of heat exchangers such as 600 and 610 are each coupled to a ー to the cooled heat transfer fluid from the heat exchanger 600 and pumped to 610 nuclear fission reactor core 20 .
[0086] 參照图16，所示的是围绕压カ容器120的内壁122并排或相邻排列多个热交換器670a，670b, 670c, 670d, 670e,670f和670g的实施例。 [0086] Referring to FIG 16, is shown around the inner wall 122 ka pressure vessel 120 are arranged side by side or a plurality of adjacent heat exchangers 670a, 670b, 670c, 670d, 670e, 670f and 670g of the embodiments. 这个实施例提供了使用中间热交換器150的另ー种配置。 This embodiment provides a use of the intermediate heat exchanger 150 is further ー configurations.
[0087] 參照图1，6，7，8，8ム，9，10，11，12和13，现在进ー步描述中间热交换器150的运行。 [0087] Referring to FIG Rousseau 1,6,7,8,8, 9,10,11,12 and 13, now running into the intermediate heat exchanger 150 ー further described. 关于这方面，核裂变反应堆堆芯20中的燃料棒40因裂变过程生成的热量被本文也称为第ー传热流体的一次传热流体吸收。 In this regard, the nuclear fission reactor core fuel rods 2040 due to heat generated by the fission process are also herein referred to as primary transfer fluid of the heat transfer fluid absorbent ー. 随着热量生成，使第一泵170运行起来,从热交換器150中抽吸或吸取第一传热流体，然后经过燃料棒50，和通过上堆芯支承板400中的流槽将第ー传热流体抽运到冷却剂池125中。 With the generated heat, running the first pump 170, a suction or draw heat transfer fluid from the first heat exchanger 150, and then through the fuel rods 50, and the flow through the slot 400 in the upper core support plate of ーpumping the heat transfer fluid into the coolant tank 125. 然后，第一泵170继续运行，通过流动通路510将第一传热流体吸取到一次流体排放空腔室430中。 Then, the first pump 170 continues to run, the flow passage 510 through the first heat transfer fluid is drawn into the primary fluid chamber 430 in the discharge chamber. 随着第一传热流体流过流动通路510，第一传热流体将与增强的传热表面550密切接触。 As the first heat transfer fluid flow through the flow passages 510, 550 to a first heat transfer fluid in close contact with the heat transfer enhancement surface. 随着第一传热流体与增强的传热表面550密切接触地流动，较冷的二次传热流体从蒸汽发生器210流出，沿着冷支路管段200，进入顶空腔530中，通过流动通道480，通过出ロ500并进入底空腔450中。 As the first heat transfer fluid and the enhanced heat transfer surfaces 550 in close contact with the flow, the secondary cooler heat transfer fluid flowing from the steam generator 210 along the cold leg pipe 200, enters the top of the cavity 530, through the flow passage 480 through the bottom and into the cavity 500 ro 450. 此后，第二传热流体通过排放ロ455从底空腔450中排放，被通过蒸汽发生器210的热支路管段190接收。 Thereafter, a second heat transfer fluid through the discharge ro 455, the bypass pipe 190 receives heat through the steam generator 210 is discharged from the cavity 450 bottom. 沿着部分热支路管段190行进和通过蒸汽发生器210的第二传热流体将它的热量传递给水体230以便生成蒸汽。 Along a portion of the heat to generate steam bypass pipe 190 and the second heat transfer fluid 210 travels will transfer its heat by the steam generator feed water 230. 使第二泵220运行起来，将较冷的二次流体从蒸汽发生器210带入顶空腔520 中。 Running the second pump 220, the cooler secondary fluid from the steam generator 210 into the cavity 520 in the top.
[0088] 仍然參照图1，6，7，8，8A，9，10，11，12和13，热量从流过流动通路510的较高温度 [0088] Referring still to FIG 1,6,7,8,8A, 9,10,11,12 and 13, heat from the higher temperature flowing through the flow path 510
的第一传热流体传递给流过流动通道480的较低温度的第二传热流体。 A first heat transfer fluid to a second heat transfer fluid flowing through the flow passage 480 of lower temperature. 这种传热通过传热构件470的壁540的传导发生。 This heat transfer occurs through the conductive wall 540 of the heat transfer member 470.
[0089] 仍然參照图1，6，7，8，8A，9，10，11，12和13，将多个相邻传热构件470隔开前述预定距离“d”，以便使一次传热流体均匀分散流过多条流动通路510。 [0089] Still referring to FIG 1,6,7,8,8A, 9,10,11,12 and 13, a plurality of adjacent heat transfer members 470 spaced a predetermined distance from the "d", the heat transfer fluid to the primary uniformly dispersed excessive flow path 510 of flow. 如前所述，将一次流体排放空腔室430做成使第一传热流体（即，一次传热流体）均匀流过一次流体排放空腔室430的形状。 As described above, the primary fluid discharge chamber of the first chamber 430 made of heat-transfer fluid (i.e., primary transfer fluid) form a uniform flow through hollow cavity 430 of the fluid discharge. 关于这方面，将一次流体排放空腔室430的上部布置成与内壁122较接近，以便一次流体排放空腔室430的上部具有比一次流体排放空腔室430的下部小的体积。 In this regard, the upper portion of the primary fluid chamber 430 to discharge chamber is arranged closer to the inner wall 122, an upper discharge chamber to a fluid chamber 430 having a fluid discharge is smaller than the lower portion 430 of the hollow chamber volume. 换句话说，一次流体排放空腔室430的体积较靠近排放ロ435的地方比较靠近进入口490的地方大。 In other words, the volume of the primary fluid discharge chamber closer to the discharge chamber 430 ro 435 relatively close to the place where a large inlet port 490. 一次流体排放空腔室430的这种形状使第一传热流体（即，一次传热流体）均匀流过一次流体排放空腔室430。 A fluid discharge chamber cavity 430 is such a shape that the first heat transfer fluid (i.e., a heat transfer fluid) flowing through the primary fluid discharge a uniform hollow chamber 430.
[0090] 例示性方法 [0090] Exemplary methods
[0091] 现在描述与核裂变反应堆系统和热交換器的示范性实施例相联系的例示性方法。 [0091] Now an exemplary embodiment of the method described in connection with exemplary fission reactor systems and heat exchangers embodiment.
[0092] 參照图17-47，为了与能够发热的核裂变反应堆关联使用，提供了组装热交換器的例示性方法。 [0092] Referring to FIGS. 17-47, in order to use the heat associated with nuclear fission reactor can be, there is provided an exemplary method of assembling a heat exchanger.
[0093] 现在转到图17，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法680从方块690开始。 [0093] Turning now to FIG. 17, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 680 starts at a block 690. 在方块700中，该方法包含接收热交換器主体。 In block 700, the method includes receiving the heat exchanger body. 在方块710中，将装置与热交換器主体耦合用于去热。 At block 710, the device body is coupled to a heat exchanger for heat. 在方块720中结束该方法。 The method ends in block 720. [0094] 參照图18，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法730从方块740开始。 [0094] Referring to FIG 18, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 730 starts at a block 740. 在方块750中，该方法包含接收热交換器主体。 In block 750, the method includes receiving the heat exchanger body. 在方块760中，该方法包含将装置与热交換器主体耦合用于去热。 At block 760, the method comprising the apparatus main body is coupled with a heat exchanger for heat removal. 在方块770中，该方法包含耦合配置为实现传热流体进入热交換器主体中的预定流动的去热装置。 In block 770, the method comprising coupling configured to achieve a predetermined flow of heat transfer fluid enters the heat exchanger to heat the body of the apparatus. 在方块780中结束该方法。 The method ends in block 780.
[0095] 參照图19，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法790从方块800开始。 [0095] Referring to FIG 19, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 790 starts at a block 800. 在方块810中，该方法包含接收热交換器主体。 In block 810, the method includes receiving the heat exchanger body. 在方块820中，将装置与热交換器主体耦合用于去热。 In block 820, the device body is coupled to a heat exchanger for heat. 在方块830中，耦合配置为实现传热流体进入热交換器主体中的预定流动的去热装置。 In block 830, the coupling configured to implement heat transfer fluid enters the apparatus to a predetermined flow of the heat exchanger body. 在方块840中，耦合配置为实现传热流体进入热交换器主体中的基本均匀流动的去热装置。 In block 840, the coupling configured to implement heat transfer fluid enters the heat removing means substantially uniform flow of the heat exchanger body. 在方块850中结束该方法。 The method ends in block 850.
[0096] 參照图20，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法860从方块870开始。 [0096] Referring to FIG 20, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 860 starts at a block 870. 在方块880中，该方法包含接收热交換器主体。 In block 880, the method includes receiving the heat exchanger body. 在方块890中，将装置与热交換器主体耦合用于去热。 In block 890, the device body is coupled to a heat exchanger for heat. 在方块900中，耦合具有增强的传热表面的去热装置。 In block 900, the coupling having an enhanced heat transfer surface of the heat removing means. 在方块910中结束该方法。 The method ends in block 910.
[0097] 參照图21，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法920从方块930开始。 [0097] Referring to FIG 21, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 920 starts at a block 930. 在方块940中，该方法包含接收热交換器主体。 In block 940, the method includes receiving the heat exchanger body. 在方块950中，将装置与热交換器主体耦合用于去热。 In block 950, the device body is coupled to a heat exchanger for heat. 在方块960中，接收将预定形状的容腔限定在其中的热交換器主体，用于实现传热流体通过热交換器主体的基本均匀流动。 In block 960, receives a predetermined shape of the cavity defined in the body of the heat exchanger therein, for achieving substantially uniform flow of heat transfer fluid through the heat exchanger body. 在方块910中结束该方法。 The method ends in block 910.
[0098] 參照图21A，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法971从方块973开始。 [0098] Referring to FIG 21A, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 971 starts at a block 973. 在方块975中，该方法包含接收热交換器主体。 In block 975, the method includes receiving the heat exchanger body. 在方块977中，将装置与热交換器主体耦合用于去热。 In block 977, the device body is coupled to a heat exchanger to heat. 在方块978中，接收无歧管热交換器主体。 In block 978, the received non-manifold heat exchanger body. 在方块979中结束该方法。 The method ends in block 979.
[0099] 參照图22，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法980从方块990开始。 [0099] Referring to FIG 22, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 980 starts at a block 990. 在方块1000中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交换器主体。 In block 1000, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1010中结束该方法。 The method ends at block 1010.
[0100] 參照图22A，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法IOlla从方块1013a开始。 [0100] Referring to FIG 22A, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger IOlla starts at a block 1013a. 在方块1015a中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 At block 1015a, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1017a中，接收用于引导池流体的流动的引导结构。 At block 1017a, the received guide structure for guiding the flow of the fluid reservoir. 在方块1019a中结束该方法。 The method ends in block 1019a.
[0101] 參照图22B，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法IOllb从方块1013b开始。 [0101] Referring to 22B, the associated pool in order to use nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger IOllb starts at a block 1013b. 在方块1015b中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1015b, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1017b中，接收用于引导池流体的流动的引导结构。 In block 1017b, the receiving guide structure for guiding the flow of the fluid reservoir. 在方块1018b中，接收配置为在热交換器主体的至少一部分内实现池流体的基本均匀流动的引导结构。 In block 1018b, the receiving guide structure configured to enable a substantially uniform flow of the fluid in the pool at least a portion of the heat exchanger body. 在方块1019b中结束该方法。 The method ends in block 1019b.
[0102] 參照图22C，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法IOllc从方块1013c开始。 [0102] Referring to FIG 22C, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger IOllc starts at a block 1013c. 在方块1015c中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1015c, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1017c中，接收含有用于引导池流体的入ロ流动的入口引导结构的热交換器主体。 In block 1017c, the receiver comprising a heat exchanger body inlet guide structure for guiding the fluid into the pool ro flow. 在方块1019c中结束该方法。 The method ends in block 1019c.
[0103] 參照图22D，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法IOlld从方块1013d开始。 [0103] Referring to FIG 22D, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger IOlld starts at a block 1013d. 在方块1015d中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1015d, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1017d中，接收含有用于引导池流体的出ロ流动的出口引导结构的热交換器主体。 The heat exchanger outlet guide body structure in block 1017d, the receiver comprising a ro for directing the flow of the fluid cell. 在方块1019d中结束该方法。 The method ends in block 1019d.
[0104] 參照图22E，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法IOlle从方块1013e开始。 [0104] Referring to FIG. 22E, in order to use pools associated with nuclear fission reactor capable of generating heat, IOlle exemplary method of assembling a heat exchanger starts at a block 1013e. 在方块1015e中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1015e, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1017e中，接收用于防止池流体与池壁接触的引导结构，该池流体布置在热交換器主体的至少一部分中。 In block 1017e, a receiver structure for preventing the guide and the wall in contact with the fluid reservoir, the reservoir fluid disposed in at least part of the heat exchanger body. 在方块1019e中结束该方法。 The method ends in block 1019e.
[0105] 參照图23，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1020从方块1030开始。 [0105] Referring to FIG 23, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1020 starts at a block 1030. 在方块1040中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1040, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1050中，接收限定非均匀形状的出ロ容腔的一部分的反应堆容器。 In block 1050, receiving a non-uniform shape defining a portion of the reactor vessel ro plenum. 在方块1060中结束该方法。 The method ends at block 1060.
[0106] 參照图24，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1070从方块1080开始。 [0106] Referring to FIG 24, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1070 starts at a block 1080. 在方块1090中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1090, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1100中，接收能够与核裂变反应堆堆芯传热连通的热交換器主体。 In block 1100, the receiving body can be the reactor core heat exchanger in heat transfer communication with the nuclear fission. 在方块1110中结束该方法。 The method ends at block 1110.
[0107] 參照图25，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1120从方块1130开始。 [0107] Referring to FIG 25, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1120 starts at a block 1130. 在方块1140中，该方法包含接收具有在其上形成的限定容腔的一部分的表面的热交換器主体。 In block 1140, the method comprising a heat exchanger body having a receiving surface defining a cavity which is formed on a part of. 在方块1150中，方法包含接收无歧管热交換器主体。 In block 1150, the method includes receiving a manifold-free heat exchanger body. 在方块1160中结束该方法。 The method ends at block 1160.
[0108] 參照图26，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1170从方块1180开始。 [0108] Referring to FIG 26, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1170 starts at a block 1180. 在方块1190中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1190, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1200中，将传热构件与热交换器主体率禹合，该传热构件限定从中通过的流动通道。 In block 1200, the heat transfer rate of the heat exchanger body member and Yu, the heat transfer member defining a flow passage therethrough. 在方块1210中结束该方法。 The method ends at block 1210.
[0109] 參照图27，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1220从方块1230开始。 [0109] Referring to FIG 27, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1220 starts at a block 1230. 在方块1240中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1240, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1250中，将传热构件与热交換器主体耦合，该传热构件限定从中通过的流动通道。 In block 1250, the heat transfer member coupled to the body heat of the heat transfer member defining a flow passage therethrough. 在方块1260中，耦合配置为实现传热流体进入热交換器主体中的预定流动的传热构件。 In block 1260, the coupling is configured to achieve a predetermined flow of heat transfer fluid enters the heat exchanger body of the heat transfer member. 在方块1270中结束该方法。 The method ends at block 1270.
[0110] 參照图28，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1280从方块1290开始。 [0110] Referring to FIG 28, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1280 starts at a block 1290. 在方块1300中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1300, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1310中，将传热构件与热交换器主体率禹合，该传热构件限定从中通过的流动通道。 In block 1310, the heat transfer rate of the heat exchanger body member and Yu, the heat transfer member defining a flow passage therethrough. 在方块1320中，耦合配置为实现传热流体进入热交換器主体中的预定流动的传热构件。 In block 1320, the heat transfer fluid coupling configured to achieve a predetermined flow entering the heat exchanger body of the heat transfer member. 在方块1330中，耦合配置为实现传热流体进入热交換器主体中的基本均匀流动的传热构件。 In block 1330, the coupling is configured to implement heat transfer fluid enters the heat exchanger body member in a substantially uniform flow. 在方块1340中结束该方法。 The method ends at block 1340.
[0111] 參照图29，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1350从方块1360开始。 [0111] Referring to FIG 29, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1350 starts at a block 1360. 在方块1370中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1370, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1380中，将传热构件与热交换器主体率禹合，该传热构件限定从中通过的流动通道。 In block 1380, the heat transfer rate of the heat exchanger body member and Yu, the heat transfer member defining a flow passage therethrough. 在方块1390中，耦合含有沿着流动通道延伸的导管的传热构件。 In block 1390, the pipe coupling comprising a heat transfer member extending along the flow path. 在方块1400中结束该方法。 The method ends at block 1400.
[0112] 參照图30，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1410从方块1420开始。 [0112] Referring to FIG 30, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1410 starts at a block 1420. 在方块1430中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1430, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1440中，将传热构件与热交換器主体耦合，该传热构件限定从中通过的流动通道。 In block 1440, the heat transfer member coupled to the body heat of the heat transfer member defining a flow passage therethrough. 在方块1450中，接收能够与核裂变反应堆堆芯传热连通的热交換器主体。 In block 1450, the receiving body can be the reactor core heat exchanger in heat transfer communication with the nuclear fission. 在方块1460中结束该方法。 The method ends at block 1460.
[0113] 參照图31，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1470从方块1480开始。 [0113] Referring to FIG 31, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1470 starts at a block 1480. 在方块1490中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1490, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1500中，将传热构件与热交換器主体耦合，该传热构件限定从中通过的流动通道。 In block 1500, the heat transfer member coupled to the body heat of the heat transfer member defining a flow passage therethrough. 在方块1510中，接收能够与核裂变反应堆堆芯传热连通的热交換器主体。 In block 1510, the receiving body can be the reactor core heat exchanger in heat transfer communication with the nuclear fission. 在方块1515中，接收能够与行波核裂变反应堆堆芯传热连通的热交換器主体。 In block 1515, the receiving body can be the reactor core heat exchanger in heat transfer communication with the nuclear fission traveling wave. 在方块1520中结束该方法。 The method ends at block 1520.
[0114] 參照图32，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1521从方块1523开始。 [0114] Referring to FIG 32, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1521 starts at a block 1523. 在方块1525中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1525, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1527中，将传热构件与热交換器主体耦合，该传热构件限定从中通过的流动通道。 In block 1527, the heat transfer member coupled to the body heat of the heat transfer member defining a flow passage therethrough. 在方块1528中，接收无歧管热交換器主体。 In block 1528, received no manifold heat exchanger body. 在方块1529中结束该方法。 The method ends in block 1529.
[0115] 參照图33，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1530从方块1540开始。 [0115] Referring to FIG 33, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1530 starts at a block 1540. 在方块1550中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1550, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1560中，将传热构件与热交換器主体耦合，该传热构件限定从中通过的流动通道。 In block 1560, the heat transfer member coupled to the body heat of the heat transfer member defining a flow passage therethrough. 在方块1570中，耦合具有在其上限定增强的传热表面的壁的传热构件。 In block 1570, the coupling member having a wall defining a heat transfer enhancement on heat transfer surfaces. 在方块1580中结束该方法。 The method ends at block 1580.
[0116] 參照图34，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1650从方块1660开始。 [0116] Referring to FIG 34, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1650 starts at a block 1660. 在方块1670中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1670, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1680中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 1680, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow paths between the plurality of heat-transfer opposing member adjacent heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块1690中结束该方法。 The method ends at block 1690.
[0117] 參照图35，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1700从方块1710开始。 [0117] Referring to FIG 35, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1700 starts at a block 1710. 在方块1720中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1720, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1730中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 1730, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow paths between the plurality of heat-transfer opposing member adjacent heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块1740中，连接配置为实现传热流体进入热交換器主体中的均匀流动的多个相邻传热构件。 In block 1740, the connection is configured to achieve uniform flow of heat transfer fluid into the plurality of heat transfer members adjacent to the main body. 在方块1690中结束该方法。 The method ends at block 1690.
[0118] 參照图36，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1760从方块1770开始。 [0118] Referring to FIG 36, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1760 starts at a block 1770. 在方块1780中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1780, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1790中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 1790, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow paths between the plurality of heat-transfer opposing member adjacent heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块1800中，接收限定非均匀形状的出ロ容腔的一部分的反应堆容器。 In block 1800, receiving a non-uniform shape defining a portion of the reactor vessel ro plenum. 在方块1810中结束该方法。 The method ends at block 1810.
[0119] 參照图37，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1820从方块1830开始。 [0119] Referring to FIG 37, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1820 starts at a block 1830. 在方块1840中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1840, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1850中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 1850, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow paths between the plurality of heat-transfer opposing member adjacent heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块I860中，接收能够与核裂变反应堆堆芯传热连通的热交換器主体。 In block I860, the receiving body can be the reactor core heat exchanger in heat transfer communication with the nuclear fission. 在方块1870中结束该方法。 The method ends at block 1870.
[0120] 參照图38，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1880从方块1890开始。 [0120] Referring to FIG 38, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1880 starts at a block 1890. 在方块1900中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1900, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1910中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 1910, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow paths between the plurality of heat-transfer opposing member adjacent heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块1915中，接收能够与核裂变反应堆堆芯传热连通的热交換器主体。 In block 1915, the receiving body can be the reactor core heat exchanger in heat transfer communication with the nuclear fission. 在方块1920中，接收能够与行波核裂变反应堆堆芯传热连通的热交換器主体。 In block 1920, the receiver can communicate with the nuclear fission reactor core heat exchanger body traveling wave. 在方块1930中结束该方法。 The method ends at block 1930.
[0121] 參照图39，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法1940从方块1950开始。 [0121] Referring to FIG 39, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 1940 starts at a block 1950. 在方块1960中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 1960, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块1970中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 1970, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow paths between the plurality of heat-transfer opposing member adjacent heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块1980中，容纳具有交叉流动取向的至少两种传热流体。 In block 1980, the receiving heat transfer fluid having at least two cross-flow orientation. 在方块1990中结束该方法。 The method ends at block 1990.
[0122] 參照图40，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2000从方块2010开始。 [0122] Referring to FIG 40, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2000 begins at block 2010. 在方块2020中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2020, the method comprising receiving a heat exchanger body cavity defined therein, the flow chamber is formed in a predetermined shape of the cavity for the heat transfer fluid to the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2030中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2030, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2040中，容纳具有相向流动取向的至少两种传热流体。 In block 2040, receiving a heat transfer fluid having at least two opposed flow orientation. 在方块2050中结束该方法。 The method ends at block 2050.
[0123] 參照图41，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2060从方块2070开始。 [0123] Referring to FIG 41, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2060 starts at a block 2070. 在方块2080中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2080, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2090中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2090, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2100中，容纳具有同向流动取向的至少两种传热流体。 In block 2100, receiving a heat transfer fluid having at least two co-current flow orientation. 在方块2110中结束该方法。 The method ends at block 2110.
[0124] 參照图42，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2120从方块2130开始。 [0124] Referring to FIG 42, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2120 starts at a block 2130. 在方块2140中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2140, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2150中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2150, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance for defining a plurality of flow passages between the plurality of heat transfer members adjacent opposing the heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2160中，耦合具有在其上限定增强的传热表面的壁以便使通过该壁的传热增加的多个相邻传热构件的至少ー个。 In block 2160, the coupling having a wall defining an enhanced heat transfer surface thereon so as to increase heat transfer through the walls of a plurality of adjacent heat transfer members of at least one ー. 在方块2110中结束该方法。 The method ends at block 2110.
[0125] 參照图43，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2180从方块2190开始。 [0125] Referring to FIG 43, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2180 starts at a block 2190. 在方块2200中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2200, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2210中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2210, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2220中，耦合具有在其上限定增强的传热表面的壁以便使通过该壁的传热增加的多个相邻传热构件的至少ー个。 In block 2220, the coupling having a wall defining an enhanced heat transfer surface thereon so as to increase heat transfer through the walls of a plurality of adjacent heat transfer members of at least one ー. 在方块2230中，耦合含有从形成强加传热表面的壁向外延伸的凸缘的多个相邻传热构件的至少ー个。 In block 2230, the coupling comprising a heat transfer member formed from a plurality of flanges extending outwardly of the heat transfer surfaces imposes a wall adjacent at least one ー. 在方块2240中结束该方法。 The method ends at block 2240.
[0126] 參照图44，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2250从方块2260开始。 [0126] Referring to FIG 44, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2250 starts at a block 2260. 在方块2270中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2270, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2280中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2280, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2290中，耦合具有在其上限定增强的传热表面的壁以便使通过该壁的传热增加的多个相邻传热构件的至少ー个。 In block 2290, the coupling having a wall defining an enhanced heat transfer surface thereon so as to increase heat transfer through the walls of a plurality of adjacent heat transfer members of at least one ー. 在方块2300中，耦合含有从形成强加传热表面的壁向内延伸的凸缘的多个相邻传热构件的至少ー个。 In block 2300, the coupling comprising a heat transfer member formed from a plurality of heat transfer surfaces imposes a flange wall extending inwardly of at least one adjacent ー. 在方块2310中结束该方法。 The method ends at block 2310.
[0127] 參照图45，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2320从方块2330开始。 [0127] Referring to FIG 45, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2320 starts at a block 2330. 在方块2340中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2340, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2350中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2350, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2360中，耦合具有在其上限定增强的传热表面的壁以便使通过该壁的传热增加的多个相邻传热构件的至少ー个。 In block 2360, the coupling having a wall defining an enhanced heat transfer surface thereon so as to increase heat transfer through the walls of a plurality of adjacent heat transfer members of at least one ー. 在方块2370中，耦合含有从形成强加传热表面的壁向外突出的结的多个相邻传热构件的至少ー个。 In block 2370, the coupling comprising a plurality of junctions are formed from the walls of heat transfer surfaces imposes projecting outwardly adjacent at least one heat transfer member ー. 在方块2380中结束该方法。 The method ends in block 2380.
[0128] 參照图46，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2390从方块2400开始。 [0128] Referring to FIG 46, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2390 starts at a block 2400. 在方块2410中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2410, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2420中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2420, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2430中，耦合含有沿着流动通道延伸的导管以便使第二传热流体流过导管的传热构件。 In block 2430, the coupling comprising a channel extending along the catheter so that the flow of heat transfer fluid to flow through the second conduit of the heat transfer member. 在方块2440中结束该方法。 The method ends at block 2440.
[0129] 參照图47，为了与能够发热的池式核裂变反应堆关联使用，组装热交換器的例示性方法2450从方块2460开始。 [0129] Referring to FIG 47, in order to use pools associated with nuclear fission reactor capable of generating heat, an exemplary method of assembling a heat exchanger 2450 starts at a block 2460. 在方块2470中，该方法包含接收将容腔限定在其中的热交换器主体，形成该容腔的形状用于传热流体到容腔中的预定流动，该热交換器主体具有在其上面形成的限定容腔的一部分的表面。 In block 2470, the method comprising receiving a heat exchanger body cavity defined therein, the shape of the cavity is formed for receiving the heat transfer fluid to a predetermined flow chamber, the heat exchanger body having formed thereon surface defining a portion of the cavity. 在方块2480中，将多个相邻传热构件与热交換器主体连接并隔开预定距离，用于限定多个相邻传热构件的相对传热构件之间的多条流动通路，以便分发传热流体流动通过多条流动通路。 In block 2480, a plurality of adjacent heat transfer member connected to the body and spaced apart a predetermined distance, a plurality of flow paths between the heat transfer members adjacent opposing defining a plurality of heat transfer member, for distribution The heat transfer fluid flow through multiple flow paths. 在方块2490中，接收无歧管热交換器主体。 In block 2490, the received non-manifold heat exchanger body. 在方块2500中结束该方法。 The method ends at block 2500.
[0130] 本领域的普通技术人员应该认识到，本文所述的部件(例如，操作)、设备、对象和伴随它们的讨论用作澄清概念的例子，可以设想出各种配置变型。 [0130] Those of ordinary skill in the art will be appreciated, components (e.g., operations) described herein, devices, objects and the discussion accompanying them as examples to clarify the concept, it is contemplated that various configuration modifications. 因此，如本文所使用，展示的特定例子以及伴随的讨论g在代表它们的更一般类别。 Thus, as used herein, for the specific examples and the accompanying discussion g is representative of their more general classes. 一般说来，任何特定例子的使用都g在代表它的类别，以及特定部件(例如，操作)、设备、和对象的未包括不应该看作是限制性的。 In general, use of any specific examples are representative of its category in g, and the specific components (e.g., operations), devices, and objects should not be construed as comprising not limiting.
[0131] 此外，本领域的普通技术人员应该懂得，前述的特定示范性过程、设备和/或技术代表像在随本文提交的权利要求书中和/或本申请中的其它地方那样，在本文其它地方讲述的更一般过程、设备和/或技木。 [0131] Further, those of ordinary skill in the art will be appreciated, specific exemplary processes, equipment and / or technical representative image of the preceding claim in the claims filed herewith and / or elsewhere in the present application as herein more generally elsewhere about the process, equipment and / or technical wood.
[0132] 虽然已经显示和描述了本文所述的当前主题的特定方面，但对于本领域的普通技术人员来说，显而易见，可以根据本文的教导，不偏离本文所述的主题及其更宽广方面地作出改变和修改，因此，所附权利要求书将像在本文所述的主题的真正精神和范围之内那样的所有这样改变和修改包括在它的范围之内。 [0132] While the subject matter described herein and described according to this particular aspect has been shown, but those of ordinary skill in the art, it is obvious, according to the teachings herein, without departing from the subject matter described herein and its broader aspects to make changes and modifications, therefore, the appended claims all such changes and modifications as as fall within the true spirit and scope of the subject matter described herein includes within its scope. 本领域的普通技术人员应该明白，一般说来，用在本文中，尤其用在所述权利要求书(例如，所附权利要求书的主要部分）中的术语一般旨在作为“开放”术语(例如，动名词术语“包括”应该理解为动名词“包括但不限干”，动名词术语“含有”应该理解为动名词“至少含有”，动词术语“包括”应该理解为动词“包括但不限干”等)。 Those of ordinary skill in the art should understand that, in general, as used herein, the term used in the particular (e.g. a main portion, the appended claims) are generally intended to claim the book as "open" terms ( For example, gerund term "comprising" should be understood gerund "including but not dry", gerund, the term "comprising" is to be understood as moving the term "comprising at least," the term verb "comprise" is to be understood as the verb "comprise, but are not limit dry ", etc.). 本领域的普通技术人员还应该明白，如果有意表示特定数量的所介绍权利要求列举项，则在权利要求中将明确列举这样的意图，而在缺乏这样的列举的情况下，则不存在这样的意图。 Those of ordinary skill in the art should further appreciate that, in the case if they wish to represent a specific number of listed items introduced claim, the claim will be explicitly recited in the claims such intent, and in the absence of such recitation, there is no intention. 例如，为了帮助人们理解，如下所附权利要求书可能包含使用介绍性短语“至少ー个”和“一个或多个”来介绍权利要求列举项。 For example, to help people understand, "ー least one" and "one or more" to introduce claim recitations following appended claims may contain usage of the introductory phrases. 但是，即使同一个权利要求包括介绍性短语“ー个或多个”或“至少ー个”以及像“ー个”或“ー种”（例如，“ー个”和/或“ー种”通常应该理解成“至少ー个”或“一个或多个”的意思）那样的不定冠词，这样短语的使用也不应该理解为暗示着通过不定冠词“ー个”或“一种”介绍权利要求列举项将包含这样所介绍权利要求列举项的任何特定权利要求限制在只包含一个这样列举项的权利要求上；对于用于介绍权利要求列举项的定冠词的使用，这同样成立。 However, even when the same claim includes the introductory phrases "ー one or more" or "at least one ー" and as "a ー" or "ー species" (e.g., "ー a" and / or "ー species" generally should be understood as "ー least one" or "one or more" means) such as the indefinite article is used, the use of such phrases should not be understood to imply that the introduction claimed by the indefinite articles "ー a" or "an" the recitation in claim containing such introduced claim recitation any particular claim containing only requirement limits in such a recitation of the claims; for a definite articles used to introduce claim recitation, which also established. 另外，即使明确列举了特定数量的所介绍权利要求列举项，本领域的普通技术人员也应该认识到，这样的列举通常应该理解成至少具有所列举数量的意思(例如，在没有其它修饰词的情况下，仅列举“两个列举项”通常意味着至少两个列举项，或两个或更多个列举项)。 Further, even if expressly enumerated specific number of an introduced claim recitation, those of ordinary skill in the art should also recognize that such recitation should typically be interpreted to mean at least the recited number (e.g., no other qualifier case, just to name "two recitations," typically means at least two recitations, or two or more recitations). 而且，在使用类似于“A、B、和C等的至少ー个”的习惯用法的那些情况下，一般说来，这样的结构g在本领域的普通技术人员理解该习惯用法的意义上使用（例如，“含有A、B、和C的至少ー个的系统”将包括但不限于只含有A，只含有B，只含有C，一起含有A和B，一起含有A和C，一起含有B和C，和/或一起含有A、B和C等的系统)。 Also in those cases, the analogous "A, B, C, etc., and at least one ー" idioms, in general, such a configuration g of ordinary skill in the art to understand the meaning of the idiom is used (e.g., "at least ー a system containing a, B, and C" would include but are not limited to containing only a, containing only B, containing only C, containing a and B together, together comprising a and C, containing B together and are C, and / or contain together with a, B and C together, etc.). 在使用类似于“A、B、或C等的至少ー个”的习惯用法的那些情况下，一般说来，这样的结构g在本领域的普通技术人员理解该习惯用法的意义上使用（例如，“含有A、B、或C的至少ー个的系统”将包括但不限于只含有A，只含有B，只含有C，一起含有A和B，一起含有A和C，一起含有B和C，和/或一起含有A、B和C等的系统)。 Those instances where a convention analogous "A, B, C, etc., or at least one of ー" idioms, in general, in such a configuration g of ordinary skill in the art to understand the meaning of the idiom used (e.g. , "comprising a, B, or C ー least one system" would include but are not limited to containing only a, containing only B, containing only C, containing a and B together, together comprising a and C together contain B and C and / or together contain a, B, and C together, etc.). 本领域的普通技术人员还应该明白，通常，无论在描述、权利要求书还是附图中，出现两个或更多个可替代项目的分隔词和/或短语应该理解成具有包括这些项目之一，这些项目的任一个，或两个项目的可能性，除非上下文另有所指。 Those of ordinary skill in the art should further appreciate that, generally, whether in the description, claims, or drawings, spacer word occurs two or more alternative items and / or phrases should be understood to include items having one of these , any of these items, or the possibility of the two projects, unless the context otherwise requires. 例如，短语“A或B”通常理解成包括“A”，“B”或“A和B”的可能性。 For example, the phrase "A or B" is generally understood to include the possibility of "A", "B" or "A and B" is.
[0133] 关于所附权利要求书，本领域的普通技术人员应该懂得，本文所列举的操作一般可以按任何次序执行。 [0133] About the appended claims, those of ordinary skill in the art should appreciate that recited operations described herein may generally be performed in any order. 此外，尽管各种操作流程按顺序展示出来，但应该明白，各种操作可以按与所例示的次序不同的其它次序执行，或者可以同时执行。 In addition, although the various operational flows out in order to show, it is to be understood that the various operations may be performed in another order than the order illustrated different, or may be performed simultaneously. 这样可替代排序的例子可以包括重叠、交错、截断、重排、递增、预备、补充、同时、反向、或其它衍生排序，除非上下文另有所指。 Examples of such alternative ordering may include overlapping, interleaved, truncation, rearrangement, incremental, preparatory, supplemental, simultaneous, reverse, or other derivatives sorting, unless the context otherwise requires. 而且，像“对...敏感”、“与...有夫”或其它过去式形容词那样的术语一般无意排斥这样的衍生，除非上下文另有所指。 Further, as "sensitive to ...", "... and married," or other past-tense adjectives are generally not intended that the term derivative such rejection, unless the context otherwise requires.
[0134] 因此，所提供的是热交換器、有关方法以及核裂变反应堆系统。 [0134] Thus, provided is a heat exchanger, and related methods nuclear fission reactor system.
[0135] 虽然本文公开了各个方面和实施例，但其它方面和实施例对于本领域的普通技术人员来说是显而易见的。 [0135] Although disclosed herein, various aspects and embodiments, but other aspects and embodiments will be apparent to those of ordinary skill in the art. 例如，參考图14，截止阀640a/640b/650a/650b的每ー个可以与布置在管道620a/620b/630a/630b的多个热电偶（未不出）的各自一个稱合。 For example, with reference to FIG. 14, each of the shut-off valve ー 640a / 640b / 650a / 650b may be disposed in a respective one of said plurality of thermocouples in engagement (not not) conduit 620a / 620b / 630a / 630b is. 取决于进入和离开热交換器600/610的传热流体的温度，控制器可以有选择地和渐进地打开和关闭截止、阀。 Depending on the temperature of the heat transfer fluid entering and leaving the heat exchanger 600/610, the controller may selectively and progressively closing off and opening the valve there. 也就是说，可以将希望在热交換器内作为热电偶感测的温度的函数的传热量预编程和存储在控制器中。 That is, the desired heat transfer in the heat exchanger as a function of the sensed thermocouple temperature pre-programmed and stored in the controller. 热交換器内的温度可以由控制器经由热电偶检测，然后控制器通过渐进地打开和关闭截止阀操作截止阀，以便使发生在热交換器内的传热与存储在控制器内的预编程值基本一致。 The temperature within the heat exchanger via a thermocouple can be detected by the controller, the controller then by progressively opening and closing operation of the shutoff valve shut-off valve, so that the heat transfer occurring within the heat exchanger preprogrammed stored in the controller basically consistent. 这样，通过使控制器自动调整阀门可以使热交換器600/610有选择地运行，以便在热交換器内提供精确的传热量。 Thus, the heat exchanger 600/610 can selectively operate by having the controller automatically adjust the valve to provide a precise amount of heat transfer in the heat exchanger.
[0136] 此外，本文公开的各个方面和实施例用于例示的目的，而无意限制本发明的范围，本发明的真正范围和精神由如下权利要求指出。 [0136] Moreover, various aspects and embodiments disclosed herein are for illustrative purposes and are not intended to limit the scope of the present invention, the true scope and spirit of the present invention requires indicated by the following claims. 另外，下面权利要求书中的所有装置或步骤以及功能元件的相应结构、材料、动作和等效物都g在包括与如具体要求的其它所要求元件结合执行功能的任何结构、材料或动作。 Further, in the following claims all means or step plus function elements corresponding structures, materials, acts, and equivalents may g to include any structure, material, or acts as the other claimed elements with the specific requirements of performing the function of binding.
1. 一种用于与池式核裂变反应堆关联使用的系统，其包含： (a)能够发热的核裂变反应堆堆芯； (b)与所述核裂变反应堆堆芯相关联的热交换器主体，所述热交换器主体能够布置在池流体中和限制池流体的池壁的内围附近；以及(C)与所述核裂变反应堆堆芯传热连通和与所述热交换器主体相关联用于移除热量的>JU装直。 1. A system associated with the pool used for nuclear fission reactor, comprising: (a) capable of heating the nuclear fission reactor core; (b) the nuclear fission reactor core and associated heat exchanger body the heat exchanger body can be disposed in a fluid reservoir surrounded by the wall and near the inner limit of the fluid reservoir; and (C) in heat transfer communication with the nuclear fission reactor core and associated with the heat exchanger body for removing heat> JU fitted straight.
2.如权利要求I所述的系统，其中所述热量移除装置配置为实现传热流体到所述热交换器主体中的预定流动。 The system of claim I as claimed in claim 2, wherein the heat removal device is configured to achieve a predetermined flow of heat transfer fluid to the heat exchanger body.
3.如权利要求I所述的系统，其中所述热量移除装置包含增强的传热表面。 The system of claim I as claimed in claim 3, wherein said heat removal means comprises an enhanced heat transfer surface.
4.如权利要求I所述的系统，其中所述热交换器主体将预定形状的容腔限定在其中，用于实现传热流体通过所述热交换器主体的基本均匀流动。 The system as claimed in claim I, wherein the heat exchanger body to a predetermined shape of the cavity defined therein, a substantially uniform flow of heat transfer fluid through the heat exchanger body.
5.如权利要求I或16所述的系统，其中所述核裂变反应堆堆芯是行波核裂变反应堆堆-IH o 5. The system of claim I or claim 16, wherein the nuclear fission reactor core is a traveling wave nuclear fission Reactor -IH o
6.如权利要求1，7或16所述的系统，其中所述热交换器主体是无歧管的。 The system of claim 7 or as claimed in claim 16, wherein said heat exchanger body is no manifold.
7. 一种用于与池式核裂变反应堆关联使用的系统，其包含： (a)限定具有内围的池壁的容器，该池壁配置为将池流体限制在其中； (b)能够布置在所述容器中和能够发热的核裂变反应堆堆芯； (C)能够与所述核裂变反应堆堆芯传热连通的热交换器主体，所述热交换器主体能够布置在池流体中和池壁的内围附近，所述热交换器主体具有在其上形成的限定容腔的一部分的表面，形成所述容腔的形状用于实现传热流体到容腔中的预定流动；以及(d)与所述核裂变反应堆堆芯传热连通和与所述热交换器主体相关联用于移除热量的>JU装直。 7. A system associated with the reactor pool for the use of nuclear fission, which comprises: (a) defining with the wall of the container around which the wall is configured to limit the pool of fluid therein; (b) can be arranged in the vessel and heat generation can be nuclear fission reactor core; (C) a heat exchanger body can be in communication with the nuclear fission reactor core heat exchanger body can be disposed in the fluid reservoir and the reservoir vicinity of the inner peripheral wall of the heat exchanger main body having a cavity defining surface portion formed thereon, the shape of the cavity is formed for achieving a predetermined flow of heat transfer fluid to the cavity; and (d ) in heat transfer communication with the nuclear fission reactor core and> JU body associated with the heat exchanger for removing heat means straight.
8.如权利要求7或16所述的系统，其中由在所述热交换器主体上形成的表面限定的容腔的该部分被传热流体占据。 7 or 8. The system according to claim 16, wherein the portion defined by a surface formed on the heat exchanger body cavity is occupied by the heat transfer fluid.
9.如权利要求7或16所述的系统，其中由在所述热交换器主体上形成的表面限定的容腔的该部分控制传热流体的流动。 9. The system of claim 7 or claim 16, wherein the portion is defined by a surface formed on the heat exchanger body cavity to control the flow of heat transfer fluid.
10.如权利要求7所述的系统，其中所述热量移除装置包含与所述热交换器主体耦合的传热构件，所述传热构件限定从中通过的流动通道。 10. The system according to claim 7, wherein said heat removal means comprises a heat transfer member coupled to the body of the heat exchanger, the heat transfer member defining a flow passage therethrough.
11.如权利要求10所述的系统，其中所述传热构件包含沿着流动通道延伸的导管。 11. The system according to claim 10, wherein the heat transfer member comprises a conduit extending along the flow path.
12.如权利要求7所述的系统，其中所述传热构件包含在其上限定增强的传热表面的壁，用于增加通过所述壁的传热。 12. The system according to claim 7, wherein the heat transfer member comprises a reinforcement in the walls defining the heat transfer surface thereon, for increasing the heat transfer through the wall.
13.如权利要求12所述的系统，其中所述传热构件包含从如下选择的传热增强特征：从所述壁向外延伸的凸缘、从所述壁向内延伸的凸缘、和从所述壁向外突出的结。 13. The system of claim 12, wherein said enhanced heat transfer from the heat transfer member comprising the following features selection: a flange extending outwardly from said wall, a flange extending inwardly from the wall, and projecting outwardly from the wall junction.
14.如权利要求7或16所述的系统，其中所述热交换器主体具有入口侧，该入口侧是无歧管的。 14. The system of claim 7 or claim 16, wherein the heat exchanger body having an inlet side, the inlet-side manifold-free.
15.如权利要求7或16所述的系统，其中所述热交换器主体具有出口侧，该出口侧具有歧管。 15. The system of claim 7 or claim 16, wherein the heat exchanger main body having an outlet side, the outlet side has a manifold.
16. 一种用于与池式核裂变反应堆关联使用的系统，其包含： Ca)限定具有内围的池壁的压力容器，该池壁配置为将池流体限制在其中；(b)布置在所述压力容器中和能够发热的核裂变反应堆堆芯； (C)能够与所述核裂变反应堆堆芯传热连通的热交换器主体，所述热交换器主体能够布置在池流体中和池壁的内围附近，所述热交换器主体具有在其上形成的在其中限定容腔的一部分的表面，形成所述容腔的形状用于实现传热流体到容腔中的预定流动；以及(d)与所述热交换器主体耦合并隔开预定距离的多个相邻传热构件，所述预定距离用于限定所述多个相邻传热构件的相对传热构件之间的多条流动通路，用于分发传热流体流动通过多条流动通路。 16. A system associated with the reactor pool for the use of nuclear fission, comprising: Ca) defining an inner periphery of the wall of the pressure vessel, that the wall is configured to limit the pool of fluid therein; (b) disposed in and said pressure vessel capable of heating the nuclear fission reactor core; heat exchanger body (C) can be in communication with the nuclear fission reactor core heat exchanger body can be disposed in the fluid reservoir and the reservoir near the inner peripheral wall of the heat exchanger main body portion having a surface defining a cavity in which is formed thereon, the shape of the cavity is formed for achieving a predetermined flow of heat transfer fluid to the cavity; and (D) and the heat exchanger coupled to the body and spaced apart a predetermined distance from the plurality of heat transfer members adjacent to the predetermined plurality of heat transfer between the opposing member defining the heat transfer member from a plurality of adjacent of flow paths for distributing the heat transfer fluid flow through multiple flow paths.
17.如权利要求16所述的系统，其中所述多个相邻传热构件的至少一个包含在其上形成增强的传热表面的壁，用于增加的通过所述壁的传热。 Comprising at least one wall formed thereon enhanced heat transfer surfaces 17. The system according to claim 16, wherein said plurality of adjacent heat transfer member for increasing the heat transfer through the wall.
18.如权利要求17所述的系统，其中所述多个相邻传热构件的至少一个包含从如下选择的传热增强特征：从所述壁向外延伸的凸缘、从所述壁向外突出的结、和沿着流动通道延伸的用于第二传热流体从中流动通过的导管。 18. The system according to claim 17, wherein said plurality of adjacent heat transfer member comprises at least one reinforcement selected from the following transfer characteristic: a flange extending outwardly from the wall, from the wall to outer projecting end, and a conduit for the second heat transfer fluid flow therethrough extending along the flow channel.
19.如权利要求16所述的系统，其中所述热交换器主体和所述多个相邻传热构件容纳具有从交叉流动取向、相向流动取向和同向流动取向中选择的取向的至少两种传热流体。 19. The system according to claim 16, wherein the heat exchanger body and the heat transfer members adjacent to accommodate a plurality of at least two cross-flow from the alignment, the alignment and orientation of the flow opposite to the flow alignment with the selected kinds of heat transfer fluid.
CN2010800535514A 2009-09-25 2010-09-22 A heat exchanger, methods therefor and a nuclear fission reactor system CN102667955A (en)
US12/586,741 2009-09-25
US12/653,656 2009-12-15
US12/653,653 2009-12-15
PCT/US2010/002604 WO2011078872A2 (en) 2009-09-25 2010-09-22 A heat exchanger, methods therefor and a nuclear fission reactor system
CN102667955A true CN102667955A (en) 2012-09-12
CN2010800535393A CN102667954A (en) 2009-09-25 2010-09-22 A heat exchanger, methods therefor and a nuclear fission reactor system
CN201080053536XA CN102667953A (en) 2009-09-25 2010-09-22 A heat exchanger, methods therefor and a nuclear fission reactor system
CN2010800535514A CN102667955A (en) 2009-09-25 2010-09-22 A heat exchanger, methods therefor and a nuclear fission reactor system
EP (3) EP2481055A2 (en)
JP (3) JP2013506130A (en)
KR (3) KR20120083432A (en)
CN (3) CN102667954A (en)
GB (3) GB2485754A (en)
WO (3) WO2011078872A2 (en)
CN103426486B (en) * 2013-08-06 2015-12-30 华北电力大学 Natural Circulation multifunctional gas lifting apparatus
陶文铨: "《传热学》", 31 December 2006, 西北工业大学出版社 *
GB2485754A (en) 2012-05-23
KR20140091691A (en) 2014-07-22 Nuclear reactors and related methods and apparatus
JPH0746157B2 (en) 1995-05-17 Radiating vessel auxiliary cooling system
US7773716B2 (en) 2010-08-10 Fast reactor having reflector control system and neutron reflector thereof
Kolev 2015 Multiphase flow dynamics 5: nuclear thermal hydraulics
Raffray et al. 2008 Engineering design and analysis of the ARIES-CS power plant
EP2862176B1 (en) 2017-08-30 Small modular reactor safety systems
EP0397509A2 (en) 1990-11-14 Indirect passive cooling system for liquid metal cooled nuclear reactors
Zheng et al. 2009 Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents
US3169117A (en) 1965-02-09 Nuclear reactor fuel paste composition
US3186913A (en) 1965-06-01 Graphite moderated nuclear reactor
EP0410667B1 (en) 1994-12-28 Liquid metal cooled nuclear reactors with passive cooling system