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21. 发明申请

US20210210222A1 DIRECT REACTOR AUXILIARY COOLING SYSTEM FOR A MOLTEN SALT NUCLEAR REACTOR 有权
公开(公告)号：US20210210222A1
公开(公告)日：2021-07-08
申请号：US17080332
申请日：2020-10-26
申请人： TerraPower, LLC
发明人： Ryan Abbott , Anselmo T. Cisneros, JR. , Daniel Flowers , Charles Gregory Freeman , Mark A. Havstad , Kevin Kramer , Jeffery F. Latkowski , Jon D. McWhirter , John R. Suyes, III
IPC分类号： G21C3/54 , G21C15/06 , G21C11/06 , G21C15/26
摘要： This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.

22. 发明授权

US10923238B2 Direct reactor auxiliary cooling system for a molten salt nuclear reactor 有权
公开(公告)号：US10923238B2
公开(公告)日：2021-02-16
申请号：US15813901
申请日：2017-11-15
申请人： TerraPower, LLC
发明人： Ryan Abbott , Anselmo T. Cisneros, Jr. , Daniel Flowers , Charles Gregory Freeman , Mark A. Havstad , Kevin Kramer , Jeffery F. Latkowski , Jon D. McWhirter , John R. Suyes, III
IPC分类号： G21C3/54 , G21C15/06 , G21C11/06 , G21C15/26
摘要： This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.

23. 发明授权

US10665356B2 Molten fuel nuclear reactor with neutron reflecting coolant 有权
公开(公告)号：US10665356B2
公开(公告)日：2020-05-26
申请号：US15584684
申请日：2017-05-02
申请人： TerraPower, LLC
发明人： Ryan Abbott , Brian C. Kelleher , William M. Kerlin , Kevin Kramer , Jeffery F. Latkowski , Jon D. McWhirter , Robert C. Petroski , Joshua C. Walter , Jesse R. Cheatham, III , Anselmo T. Cisneros, Jr. , Ken Czerwinski , Bassem S. El-Dasher , Daniel Flowers , Charles Gregory Freeman , Mark A. Havstad , Christopher J. Johns
IPC分类号： G21C15/28 , G21C3/54 , G21C1/32 , G21C15/25 , G21C15/02 , G21C7/27 , G21C11/06 , G21C7/22 , G21C1/02
摘要： Configurations of molten fuel salt reactors are described that utilize neutron-reflecting coolants or a combination of primary salt coolants and secondary neutron-reflecting coolants. Further configurations are described that circulate liquid neutron-reflecting material around an reactor core to control the neutronics of the reactor. Furthermore, configurations which use the circulating neutron-reflecting material to actively cool the containment vessel are also described.

24. 发明授权

US10510450B2 Heat pipe molten salt fast reactor with stagnant liquid core 有权
公开(公告)号：US10510450B2
公开(公告)日：2019-12-17
申请号：US15701477
申请日：2017-09-12
申请人： WESTINGHOUSE ELECTRIC COMPANY, LLC
发明人： Yasir Arafat , Jurie Van Wyk , Edward J. Lahoda
IPC分类号： G21C17/10 , G21C7/10 , G21C9/02 , G21C1/02 , G21C15/257 , G21C3/54 , G21C11/06
摘要： A molten salt reactor includes a containment vessel, a reactor core, a neutron reflector spaced from the containment vessel, and liquid fuel enclosed within the core. The liquid fuel is comprised of a nuclear fission material dissolved in a molten salt. A heat exchanger is positioned external to the containment vessel. A plurality of heat transfer pipes are provided for transferring heat from the core to the heat exchanger. Each pipe has a first and a second end. The first end of each pipe is positioned within the reactor core for absorbing heat from the fuel. The heat exchanger receives the second end of each heat transfer pipe. At least two or more reactor shut down systems are provided. At least one shut down system may be a passive system and at least one or both shut down systems may be an active or a manually operated system.

25. 发明授权

US10163531B2 Reactivity control in a molten salt reactor 有权
公开(公告)号：US10163531B2
公开(公告)日：2018-12-25
申请号：US15516839
申请日：2015-03-09
申请人： Ian Richard Scott
发明人： Ian Richard Scott
IPC分类号： G21C7/22 , G21C1/03 , G21C1/14 , G21C7/04 , G21C19/31 , G21C3/54 , G21C7/24 , G21C15/247
摘要： Methods of controlling the reactivity of a molten salt fission reactor. The molten salt fission reactor comprises a core and a coolant tank (101), the core comprising fuel tubes (103) containing a molten salt fissile fuel, and the coolant tank containing a molten salt coolant (102), wherein the fuel tubes are immersed in the coolant tank. The methods comprise dissolving a neutron absorbing compound in the molten salt coolant, the neutron absorbing compound comprising a halogen and a neutron absorbing element. The first method further comprises reducing the neutron absorbing compound to a salt of the halogen and an insoluble substance comprising the neutron absorbing element, the halogen being fluorine or chlorine, wherein the insoluble substance is not volatile at a temperature of the coolant during operation of the reactor. In the second method the one or more neutron absorbing compounds are chosen such that reduction of the neutron absorbing capacity of the one or more neutron absorbing compounds due to absorption of neutrons compensates for a fall in reactivity of the core in order to control fission rates in the core. Apparatus for implementing the methods are also provided.

26. 发明申请

US20180047467A1 ELECTRO-SYNTHESIS OF URANIUM CHLORIDE FUEL SALTS 审中-公开
公开(公告)号：US20180047467A1
公开(公告)日：2018-02-15
申请号：US15673188
申请日：2017-08-09
申请人： TerraPower, LLC
发明人： Ken Czerwinski , Bassem S. El-Dasher , William M. Kerlin , Aaron J. Unger
IPC分类号： G21C3/54 , B01J19/08 , C01G43/08
CPC分类号： G21C3/54 , B01J19/087 , B01J2219/0803 , B01J2219/0879 , C01G43/08 , C01P2006/44 , C25B1/00 , C25B11/04
摘要： This disclosure describes systems and methods for synthesizing UCl3 from UCl4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl4, UCl3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl3—UCl4—NaCl or UCl3—NaCl fuel salt composition from UCl4—NaCl.

27. 发明申请

US20170301418A1 SALT COMPOSITIONS FOR MOLTEN SALT REACTORS 审中-公开
公开(公告)号：US20170301418A1
公开(公告)日：2017-10-19
申请号：US15380473
申请日：2016-12-15
申请人： Elysium Industries Limited
发明人： Andrew Mccall Dodson , Michael Forrest Simpson , Edward Pheil , Michael E. Hanson
IPC分类号： G21C3/54
CPC分类号： G21C3/54 , Y02E30/38
摘要： A salt composition for use as a fuel in a nuclear reactor is provided. The salt composition can include carrier salts having mixtures of one or more chloride salts or one or more chloride salts and one or more fluoride salts and fuel salts including one or more chloride salts. The carrier salts can include alkali and/or alkaline earth cations, while the fuel salts can include actinide cations. The salt composition has a lower melting temperature, less corrosive redox properties, and allows proliferation-safe retention of actinides and concurrent removal of some fission products, as compared to other salts employed in molten salt reactors. Optionally, the salt composition can include one or more metal halides for further decreasing the melting point and/or increasing the boiling point of the composition, thereby increasing the range of the liquid phase of the salt composition.

28. 发明申请

US20170243664A1 REACTIVITY CONTROL IN A MOLTEN SALT REACTOR 审中-公开
公开(公告)号：US20170243664A1
公开(公告)日：2017-08-24
申请号：US15516839
申请日：2015-03-09
申请人： Ian Richard SCOTT
发明人： Ian Richard SCOTT
IPC分类号： G21C7/22 , G21C3/54 , G21C15/247 , G21C7/24 , G21C19/31
CPC分类号： G21C7/22 , G21C1/03 , G21C1/14 , G21C3/54 , G21C7/04 , G21C7/24 , G21C15/247 , G21C19/31 , G21Y2004/101 , Y02E30/34 , Y02E30/35 , Y02E30/39
摘要： Methods of controlling the reactivity of a molten salt fission reactor. The molten salt fission reactor comprises a core and a coolant tank (101), the core comprising fuel tubes (103) containing a molten salt fissile fuel, and the coolant tank containing a molten salt coolant (102), wherein the fuel tubes are immersed in the coolant tank. The methods comprise dissolving a neutron absorbing compound in the molten salt coolant, the neutron absorbing compound comprising a halogen and a neutron absorbing element. The first method further comprises reducing the neutron absorbing compound to a salt of the halogen and an insoluble substance comprising the neutron absorbing element, the halogen being fluorine or chlorine, wherein the insoluble substance is not volatile at a temperature of the coolant during operation of the reactor. In the second method the one or more neutron absorbing compounds are chosen such that reduction of the neutron absorbing capacity of the one or more neutron absorbing compounds due to absorption of neutrons compensates for a fall in reactivity of the core in order to control fission rates in the core. Apparatus for implementing the methods are also provided.

29. 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。

30. 发明申请

US20230127207A1 METHODS AND SYSTEMS FOR IMPROVED TEST FUEL REACTOR 有权
公开(公告)号：US20230127207A1
公开(公告)日：2023-04-27
申请号：US18045398
申请日：2022-10-10
申请人： TerraPower, LLc
发明人： Ryan Abbott , Darryl Appelgate , Haley Barsa , Michael T. Blatnik , Karl Britsch , Anselmo T. Cisneros, JR. , Brian C. Kelleher , Samuel S. Goodrich , Ramesh Rajasekaran , Daniel J. Walter , Kent E. Wardle , Matthew D. Wargon
IPC分类号： G21C11/06 , G21C3/54
摘要： A simple nuclear reactor in which most of the reflector material is outside of the reactor vessel is described. The reactor vessel is a cylinder that contains all of the fuel salt and a displacement component, which may be a reflector, in the upper section of the reactor vessel. Other than the displacement component, the reflector elements including a radial reflector and a bottom reflector are located outside the vessel. The salt flows around the outside surface of the displacement component through a downcomer heat exchange duct defined by the exterior of the displacement component and the interior surface of the reactor vessel. This design reduces the overall size of the reactor vessel for a given volume of salt relative to designs with internal radial or bottom reflectors.

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