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1. 发明授权

US11798694B2 Molten fuel nuclear reactor 有权
公开(公告)号：US11798694B2
公开(公告)日：2023-10-24
申请号：US17076309
申请日：2020-10-21
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, Jr. , Charles Gregory Freeman , Kevin Kramer , Jeffery F. Latkowski
IPC分类号： G21C7/28 , G21C3/54 , G21C7/22 , G21C7/27 , G21C1/02 , G21C1/22 , G21C15/28 , G21C1/32 , G21C11/06 , G21C15/02
CPC分类号： G21C7/28 , G21C3/54 , G21C7/22 , G21C7/27 , G21C1/026 , G21C1/22 , G21C1/326 , G21C11/06 , G21C15/02 , G21C15/28 , Y02E30/30
摘要： A molten fuel salt nuclear reactor core assembly including a fluid neutron reflecting material defining a fast spectrum fuel volume configured to breed fissile fuel from fertile fuel, a first inlet channel, and a first outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the fast spectrum fuel volume. The core assembly also includes a set of neutron absorbing members sized to fit within the fast spectrum fuel volume. The set of neutron absorbing members define a thermal spectrum fuel volume for a fission reaction of the fissile fuel, a second inlet channel, and a second outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the thermal spectrum fuel volume.

2. 发明申请

US20170294241A1 CORROSION REDUCTION IN A MOLTEN SALT REACTOR 审中-公开
公开(公告)号：US20170294241A1
公开(公告)日：2017-10-12
申请号：US15342513
申请日：2016-11-03
申请人： Elysium Industries Limited
发明人： Andrew McCall Dodson , Michael Simpson , William Wangard , Edward Pheil
IPC分类号： G21C1/32 , B01J19/00 , C23F13/16 , C23F15/00 , H01M4/02 , G21C1/22 , B01J19/02
CPC分类号： C23F13/16 , B01J19/0013 , B01J19/02 , C23F13/04 , C23F13/14 , C23F13/22 , C23F2201/00 , C23F2213/21 , G21C1/03 , G21C1/22 , G21C17/022 , G21C19/31 , Y02E30/34 , Y02E30/35
摘要： A molten salt reactor comprising a reactor vessel and a molten salt contained within the reactor vessel. There is a corrosion reduction unit configured to process the molten salt to maintain an oxidation reduction ratio, (E(o)/E(r)), in the molten salt at a substantially constant level, wherein E(o) is an element (E) at a higher oxidation state (o) and E(r) is the element (E) at a lower oxidation state (r).

3. 发明申请

US20150228361A1 Converter Reactor for Thermal Neutrons 审中-公开
标题翻译：用于热中子的转换器
公开(公告)号：US20150228361A1
公开(公告)日：2015-08-13
申请号：US14367692
申请日：2011-12-21
申请人： Alexander Potemkin
发明人： Alexander Potemkin
IPC分类号： G21C1/22 , G21C3/52
CPC分类号： G21C1/22 , C04B35/583 , C04B35/806 , C04B2235/386 , C04B2235/5244 , C04B2235/5276 , G21C3/04 , G21C3/52 , G21C5/126 , G21C15/02 , Y02E30/38
摘要： A converter reactor is provided. The converter reactor includes a low-pressure housing in which an active zone of the reactor is located. The reactor includes vertical columns of a side reflector and a moderator, channels for heat carrier flow and fuel elements having fuel rods in the central openings of the moderator columns. The low-pressure housing is made of a high-strength titanium alloy with an inner protective boron nitride composite material. The heat carrier in which the active zone is immersed is polysilazane-based. The interior of the fuel rods is filled with a uranium-plutonium melt. Cavities of the upper ends of the fuel rods communicate with fuel element cavities and fission product collectors of the fuel elements at the same pressure.
摘要翻译：提供了一个转换器反应器。转换器反应器包括其中位于反应器的活动区域的低压壳体。反应器包括侧反射器和慢化器的垂直柱，用于热载体流的通道和在调节塔的中心开口中具有燃料棒的燃料元件。低压外壳由具有内部保护性氮化硼复合材料的高强度钛合金制成。活性区浸渍的载体是聚硅氮烷基。燃料棒的内部填充有铀 - 钚熔体。燃料棒的上端的腔与相同压力下的燃料元件腔和燃料元件的裂变产物收集器连通。

4. 发明申请

US20120051481A1 TWO-FLUID MOLTEN-SALT REACTOR 有权
标题翻译：双流体盐酸反应器
公开(公告)号：US20120051481A1
公开(公告)日：2012-03-01
申请号：US13290711
申请日：2011-11-07
申请人： Frank H. Shu
发明人： Frank H. Shu
IPC分类号： G21C1/06 , G21C1/22 , G21C1/16
CPC分类号： G21C13/02 , G21C1/22 , G21C1/28 , G21C5/02 , G21C15/02 , Y02E30/40
摘要： A reactor vessel includes a plenum and a reactor core with first and second sets of channels. A blanket salt flows through the first set of channels, and a fuel salt flows through the second set of channels. The plenum receives the blanket salt from the first set of channels. The blanket salt provides a breed-stock for a fission reaction in the fuel salt and transfers heat generated by the fission reaction without mixing with the fuel salt.
摘要翻译：反应堆容器包括具有第一和第二组通道的增压室和反应堆堆芯。覆盖的盐流过第一组通道，燃料盐流过第二组通道。通风室从第一组通道接收毯子盐。覆盖盐提供了燃料盐中的裂变反应的品种，并且传递由裂变反应产生的热而不与燃料盐混合。

5. 发明授权

US4415525A Heterogeneous gas core reactor 失效
标题翻译：异质气体核心反应堆
公开(公告)号：US4415525A
公开(公告)日：1983-11-15
申请号：US184134
申请日：1980-09-04
申请人： Nils J. Diaz , Edward T. Dugan
发明人： Nils J. Diaz , Edward T. Dugan
IPC分类号： G21C1/10 , G21C1/22
CPC分类号： G21C1/22 , G21C1/10 , Y02E30/40
摘要： A heterogeneous gas core nuclear reactor comprising a core barrel provided interiorly with an array of moderator-containing tubes and being otherwise filled with a fissile and/or fertile gaseous fuel medium. The fuel medium may be flowed through the chamber and through an external circuit in which heat is extracted. The moderator may be a fluid which is flowed through the tubes and through an external circuit in which heat is extracted. The moderator may be a solid which may be cooled by a fluid flowing within the tubes and through an external heat extraction circuit. The core barrel is surrounded by moderator/coolant material. Fissionable blanket material may be disposed inwardly or outwardly of the core barrel.
摘要翻译：一种异质气体核反应堆，包括内部设置有一定数量的含缓和剂管的核心筒，另外填充有易裂变和/或可育气态燃料介质。燃料介质可以流过腔室并且通过提取热量的外部回路。调节剂可以是流过管子并通过提取热量的外部回路的流体。调节剂可以是固体，其可以通过在管内流动的流体和通过外部热提取回路来冷却。核心筒被慢化剂/冷却剂材料包围。可裂变橡皮布材料可以设置在芯筒的内侧或外侧。

6. 发明授权

US4234383A Actinide nitride-fueled reactor and continuous method of operating the same 失效
标题翻译：锕系氮化物燃料反应器及其连续操作方法
公开(公告)号：US4234383A
公开(公告)日：1980-11-18
申请号：US905745
申请日：1978-05-15
申请人： Robert N. Anderson , Norman A. D. Parlee
发明人： Robert N. Anderson , Norman A. D. Parlee
IPC分类号： G21C1/22 , G21C7/30 , G21C7/02 , G21C15/00 , G21C19/00
CPC分类号： G21C1/22 , G21C7/30 , G21Y2002/201 , G21Y2002/601 , G21Y2004/30 , G21Y2004/302 , G21Y2004/402 , Y02E30/39
摘要： An actinide nitride-fueled nuclear reactor and a method of operation therefor, including continuous in situ removal of fission products and optional addition of fuel-forming actinide material as the reaction proceeds. The reactor employed has a fuel system comprising a critical mass of a nitride of an actinide metal in contact with a non-critical solution of the actinide metal in a molten metal solvent of low neutron adsorption cross section such as tin, said fuel system being maintained under a nitrogen atmosphere in an inert, refractory vessel such as graphite which is non-conducive to the formation of actinide oxides. Fission products formed are continuously exchanged with the actinide metal dissolved in the molten metal solvent as the nuclear reaction proceeds, with equivalent amounts of actinide nitride being formed and precipitated into the critical mass as fission products are dissolved in the molten metal solution. Temperature excursions tend to be suppressed by the nitride decomposition which ensues as temperatures are increased without any balancing increase in nitrogen pressures to restore the equilibrium.
摘要翻译：一种锕系氮化物燃料核反应堆及其操作方法，包括连续原位除去裂变产物，随着反应的进行，任选添加燃料形成锕系材料。所使用的反应器具有燃料系统，其包括锕系金属的氮化物的临界质量，其与低中子吸附截面（如锡）的熔融金属溶剂中的锕系金属的非临界溶液接触，所述燃料体系被保持在氮气气氛下在惰性耐火容器如石墨中，这不利于形成锕系氧化物。当核反应进行时，形成的裂变产物与溶解在熔融金属溶剂中的锕系金属连续交换，当裂变产物溶解在熔融金属溶液中时，形成等量的锕系氮化物并沉淀到临界物质中。温度偏移倾向于通过氮化物分解来抑制，随着温度的升高，氮化物分解不会在氮气压力下平衡增加以恢复平衡。

7. 发明授权

US4085582A Wall and nozzle assembly for colloidal core reactor 失效
标题翻译：胶体核心反应器的壁和喷嘴组件
公开(公告)号：US4085582A
公开(公告)日：1978-04-25
申请号：US738915
申请日：1976-11-04
申请人： Brian A. Hausfeld
发明人： Brian A. Hausfeld
IPC分类号： F25B9/04 , G21C1/22 , G21D1/00
CPC分类号： F25B9/04 , G21C1/22 , G21Y2002/50 , G21Y2004/30 , Y02E30/40
摘要： A wall and exit nozzle assembly for a particle confined vortex system having a plurality of annular slots in the wall adjacent the exit throat nozzle. The wall and exit nozzle assembly includes a manifold ring, feeder channels to supply a gas flow through the annular slots. Swirl slots are provided in the assembly adjacent the annular slots to impart a rotational velocity to the gas flow. Additional gas ejection slots are provided adjacent the nozzle throat. Swirl slots are provided to supply a rotational velocity to the gas leaving the ejection slots in the nozzle throat.
摘要翻译：一种用于颗粒限制涡旋系统的壁和出口喷嘴组件，其在邻近出口喉部喷嘴的壁中具有多个环形槽。壁和出口喷嘴组件包括歧管环，供给通道以供给通过环形槽的气流。旋转槽设置在邻近环形槽的组件中以赋予气流的旋转速度。在喷嘴喉部附近设置附加的气体喷射槽。提供涡流槽以向离开喷嘴喉部中的喷射槽的气体提供旋转速度。

8. 发明授权

US4045286A Molten fuel-salt reactor 失效
标题翻译：熔融燃料盐反应堆
公开(公告)号：US4045286A
公开(公告)日：1977-08-30
申请号：US642996
申请日：1975-12-22
申请人： Jacques Marcel Blum , Michel Grenon , Edmond Ventre
发明人： Jacques Marcel Blum , Michel Grenon , Edmond Ventre
IPC分类号： G21C1/00 , G21C1/03 , G21C1/22 , G21C1/32 , G21C15/02 , G21C15/24 , G21C3/54
CPC分类号： G21C1/32 , G21C1/03 , G21C1/22 , G21C15/02 , G21C15/24 , G21C3/54 , G21Y2002/103 , G21Y2002/30 , G21Y2004/30 , Y02E30/34 , Y02E30/35
摘要： In a molten-salt reactor, a common vessel contains the reactor core, a neutron-moderating mass pierced by passages for the circulation of the fuel salt, at least one primary heat exchanger which is located close to the reactor core and through which the hot fuel salt passes after discharge from the core, pumps for circulating the cold fuel salt from the heat exchangers back into the reactor core. The free spaces defined within the reactor vessel between the core, the heat exchangers and the pumps except for the passages in which the molten fuel salt is circulated are packed with material which is compatible with the fuel salt.
摘要翻译：在熔盐反应器中，公共容器包含反应堆芯，用于燃料盐循环的通道刺穿的中子调节剂，至少一个位于反应堆芯附近的主要热交换器，通过该热交换器将热燃料盐从核心排出后通过，用于将冷燃料盐从热交换器循环回到反应堆堆芯中。在核心，热交换器和除了熔融燃料盐循环的通道之外的反应器容器内限定的自由空间用与燃料盐相容的材料填充。

9. 发明授权

US3861998A Method of operating a neutronic reactor 失效
标题翻译：操作中和反应器的方法
公开(公告)号：US3861998A
公开(公告)日：1975-01-21
申请号：US36304173
申请日：1973-05-23
申请人： EXXON RESEARCH ENGINEERING CO
发明人： OKRENT EUGENE H , TARMY BARRY L
IPC分类号： G21C1/22 , G21C19/307
CPC分类号： G21C1/22 , G21C19/307 , G21Y2002/103 , G21Y2002/201 , G21Y2004/40 , Y02E30/40
摘要： A novel system and method of operating a fluid fuel nuclear reactor is provided in which heat for power generation is transferred directly from the fluid fuel to a purge material while the purge material simultaneously sweeps neutron-absorbing fission products from the fluid fuel.
摘要翻译：提供了一种操作流体燃料核反应堆的新型系统和方法，其中用于发电的热量直接从流体燃料转移到吹扫材料，同时吹扫材料同时从流体燃料中扫除中子吸收裂变产物。

10. 发明授权

US3446703A Method of operating a nuclear reactor 失效
标题翻译：操作核反应堆的方法
公开(公告)号：US3446703A
公开(公告)日：1969-05-27
申请号：US3446703D
申请日：1967-11-15
申请人： ATOMIC ENERGY COMMISSION
发明人： LYONS MARK F , WEIDENBAUM BERNHARDT
IPC分类号： G21C1/02 , G21C1/22 , G21C3/04 , G21C3/17 , G21C3/24 , G21C3/02
CPC分类号： G21C3/24 , G21C1/02 , G21C1/22 , G21C3/04 , G21C3/041 , G21C3/17 , G21Y2002/201 , G21Y2004/30 , G21Y2004/302 , Y02E30/34 , Y10S376/901

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