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公开(公告)号：US3280011A
公开(公告)日：1966-10-18
申请号：US21626662
申请日：1962-07-18
申请人： DIAMOND ALKALI CO
IPC分类号： B01J13/00 , C01F15/00 , C01G43/00 , C01G43/01 , C01G56/00 , G21C1/24 , G21C1/26 , G21C3/48 , G21C3/54 , H04B1/68 , H04K1/00 , H04L9/00
CPC分类号： B01D61/44 , B01J13/0017 , B01J13/0047 , C01F15/00 , C01G43/00 , C01G43/01 , C01G56/00 , C01G56/004 , C01G56/005 , G21C1/24 , G21C1/26 , G21C3/48 , G21Y2002/104 , G21Y2004/10 , Y02E30/38
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公开(公告)号：US3063923A
公开(公告)日：1962-11-13
申请号：US81708759
申请日：1959-06-01
申请人： MAYER STANLEY W
发明人： MAYER STANLEY W
CPC分类号： G21C3/54 , G21C1/24 , G21C5/20 , G21C5/22 , G21Y2002/104 , G21Y2004/10 , Y02E30/38
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43.发明公开公开(公告)号：US20240203613A1
公开(公告)日：2024-06-20
申请号：US18542987
申请日：2023-12-18
摘要： A molten salt nuclear reactor of the fast neutron reactor type may be designed as a reactor vessel free of moderator or at the very least of a moderator enabling a reactor to be qualified as a thermal neutron reactor, having a shape exhibiting symmetry of revolution surrounded by another vessel at the periphery of the reactor vessel thereby delimiting a guard gap filled with an inert liquid salt which acts as a coolant for removing the decay heat from the reactor by conduction through the reactor vessel.
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公开(公告)号：US11862354B2
公开(公告)日：2024-01-02
申请号：US18044479
申请日：2021-09-01
申请人： Ian Richard Scott
发明人： Ian Richard Scott
摘要： A passive nuclear reactor control device. The passive nuclear reactor control device comprises a sealed chamber, which comprises a reservoir and a tube in fluid communication with the reservoir. A molten salt is within the sealed chamber, the molten salt being a eutectic mixture of a monovalent metal halide, and a fluoride or chloride of one or more lanthanides and/or a fluoride or chloride of hafnium. A gas is within the sealed chamber, and the gas does not react with the molten salt.
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45.发明授权公开(公告)号：US11791056B2
公开(公告)日：2023-10-17
申请号：US17685324
申请日：2022-03-02
申请人： Thomas J Wielenga
发明人： Thomas J Wielenga
摘要： A nuclear reactor controlled by moving a liquid fuel between a reservoir and chambers in the core is provided. No pumps or moving parts within the reactor vessel are needed to move the fuel. The control system moves the liquid fuel between the core and the reservoir by moving a separate control gas. It can monitor the internal state of the core through the control connections. The fuel chamber is shaped so that evolved gases escape the core and can be collected at the control connections. The core reverts to a safe state on power failure.
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公开(公告)号：US11621098B2
公开(公告)日：2023-04-04
申请号：US17444483
申请日：2021-08-05
申请人： Texas Thorium LLC
摘要： A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example includes the steps of providing a vessel containing a molten salt fuel, generating a proton beam externally to the vessel, where the externally generated proton beam is of an energy level sufficient to interact with material within a fuel rod in the vessel to produce (p, n) reactions resulting in the generation of neutrons at a first energy level. Neutrons generated within the vessel through the (p, n) reactions are utilized to produce a fission reaction which increases the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.
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公开(公告)号：US20220028569A1
公开(公告)日：2022-01-27
申请号：US17427050
申请日：2020-01-31
申请人： Seaborg ApS
发明人： Troels Schönfeldt , Jimmy Sølvsteen Nielsen , Eirik Eide Pettersen , Andreas Vigand Pedersen , Daniel John Cooper , Ask Emil Løvshall-Jensen
摘要： The present invention relates to a device adapted for producing energy by nuclear fission, the device comprising a core container of a core container material, which core container encloses an inner tubing of an inner tubing material, the inner tubing and/or the core container having an inlet and an outlet, the device further comprising a molten halide salt located in the core container or in the inner tubing, wherein the inner tubing comprises one or more sections consisting of single crystal corundum. The invention further relates to methods of controlling nuclear fission processes using the device and to the use of a corundum tube as a structural material in a nuclear fission device. The invention provides improved economy in molten salt nuclear fission processes.
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公开(公告)号：US20210343431A1
公开(公告)日：2021-11-04
申请号：US17368576
申请日：2021-07-06
申请人： TerraPower, LLC
摘要： A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.
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公开(公告)号：US11158431B2
公开(公告)日：2021-10-26
申请号：US16622729
申请日：2018-06-15
申请人： Seaborg ApS
发明人： Troels Schönfeldt , Jimmy S. Nielsen , Eirik E. Pettersen , Andreas V. Pedersen , Daniel J. Cooper
摘要： Device for producing energy by nuclear fission, and methods of using same. The device comprises a core container of a core container material, which core container encloses an inner tubing of an inner tubing material. The inner tubing and/or the core container has(have) an inlet and an outlet. The device also comprises a molten fuel salt with a fissionable material and a molten moderator salt comprising metal hydroxide(s), metal deuteroxide(s) or a combination thereof and a redox-element having a reduction potential, which is larger than that of the inner tubing material or of the inner tubing material and the core container material. The molten moderator salt is located in the core container, and the molten fuel salt is located in the inner tubing. Alternatively, the molten fuel salt is located in the core container, and the molten moderator salt is located in the inner tubing.
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公开(公告)号：US11136245B2
公开(公告)日：2021-10-05
申请号：US16709449
申请日：2019-12-10
发明人： John Benson , Matthew Memmott
IPC分类号： G21C3/54 , C01G43/06 , C01D3/02 , C01D15/04 , C01F5/30 , C01F11/22 , C01D3/04 , G21C5/18 , G21C19/28 , G21C1/02
摘要： Some embodiments include a method comprising: flowing a molten salt out of a molten salt reactor at a first temperature, heating the molten salt reactor to a second temperature above the melding point of the second salt mixture causing the second salt mixture to melt; flowing the second salt mixture out of the molten salt reactor; flowing a third salt mixture into the molten salt reactor; and cooling the molten salt reactor from the second temperature to a third temperature causing the third salt mixture to solidify on the interior surface of the housing. In some embodiments, the molten salt may include a first salt mixture comprising at least uranium. In some embodiments, the first temperature is a temperature above the melting point of the first salt mixture.
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