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公开(公告)号：US20240229744A1
公开(公告)日：2024-07-11
申请号：US18403448
申请日：2024-01-03
申请人： Ajay P. Kothari
发明人： Ajay P. Kothari
摘要： Methods and systems for propelling an air vehicle with a molten salt reactor, a first heat exchanger, and a second heat exchanger are disclosed. A hot liquid molten salt from the molten salt reactor heats a fluid in the first heat exchanger to produce a hot fluid. The hot fluid heats air in the second heat exchanger to produce heated air which passes through a nozzle to propel the air vehicle.
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公开(公告)号：US20240134073A1
公开(公告)日：2024-04-25
申请号：US18379901
申请日：2023-10-13
申请人： UT-Battelle, LLC
发明人： Richard REED , Eva URIBE , Louise G. WORRALL , Thomas J. HARRISON
摘要： A system and a method for the remote monitoring of an irradiated salt mass within a decay enclosure is provided. The system and the method determine a mass ratio of a first radioisotope relative to a second radioisotope, the second radioisotope having a significantly shorter half-life than the first radioisotope. In addition, the second radioisotope includes a shorter half-life than an effective half-life of the decay enclosure, and the first radioisotope includes a longer half-life than the effective half-life of the decay enclosure. The mass ratio quickly decreases outside of a target range after material diversion, while remaining below the target range for several years. As a consequence, the isotopic mass ratio presents a rapid and enduring indicator of inventory change, which is of extreme importance in detecting a diversion of the irradiated salt mass, which remains a potential proliferation target.
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公开(公告)号：US20240062923A1
公开(公告)日：2024-02-22
申请号：US18452011
申请日：2023-08-18
申请人： ABILENE CHRISTIAN UNIVERSITY , Board of Regents, The University of Texas System , The Texas A&M University System
发明人： Jonathan Scherr , Timothy Head , Derek Haas , Jack Shoemate , Pavel Tsvetkov , Rusty Towell
摘要： A molten salt reactor system includes a fuel salt system configured to circulate a molten salt through a reactor vessel. The molten salt reactor system further includes an inert gas system fluidically coupled with the fuel salt system and configured to maintain a pressurized volume fluidically between the molten salt and a drain tank by circulating an inert gas along a first inert flow path. The molten salt reactor system further includes an equalization system configured to equalize pressure between all head spaces of the molten salt reactor system including the reactor vessel and the drain tank in response to a shutdown event. The inert gas system is configured to cease maintenance of the pressurized volume in response to the shutdown event.
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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
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.
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公开(公告)号：US20230041327A1
公开(公告)日：2023-02-09
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 of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton’s interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction 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：US20230005628A1
公开(公告)日：2023-01-05
申请号：US17833530
申请日：2022-06-06
申请人： BK Clean Energy LLC
摘要： A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.
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7.发明申请公开(公告)号：US20220227683A1
公开(公告)日：2022-07-21
申请号：US17149937
申请日：2021-01-15
发明人： Abdulaziz S. Al-Qasim , Yuguo Wang
摘要： A system for a carbon neutral cycle of gas production may include a molten salt reactor configured to generate zero carbon dioxide (CO2) emissions electricity. The system may include a desalination unit configured to receive the zero-CO2 emissions electricity from the molten salt reactor and produce a desalinated water. The system may include an electrolysis unit configured to be powered by the zero-CO2 emissions electricity generated by the molten salt reactor and generate hydrogen (H2) and oxygen (O2) from the desalinated water. The system may include an oxy-combustion unit configured to receive and combust a hydrocarbon fuel with the O2 from the electrolysis unit to produce electricity and CO2. The system may include a CO2 capture system adapted to capture the CO2 produced by the oxy-combustion unit and a catalytic hydrogenation unit configured to receive and convert H2 from the electrolysis unit and CO2 from the CO2 capture system to produce the hydrocarbon fuel.
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公开(公告)号：US11367536B2
公开(公告)日：2022-06-21
申请号：US16824125
申请日：2020-03-19
申请人： TerraPower, LLC
发明人： Ryan Abbott , Anselmo T. Cisneros, Jr. , Daniel Flowers , Charles Gregory Freeman , Mark A. Havstad , Christopher J. Johns , Brian C. Kelleher , Kevin Kramer , Jeffery F. Latkowski , Jon D. McWhirter
IPC分类号： G21C1/03 , G21C1/32 , G21C1/22 , G21C15/243 , G21C15/02 , G21C15/26 , G21C11/06 , G21C1/14 , G21C3/54 , G21C15/28
摘要： Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.
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公开(公告)号：US20220139577A1
公开(公告)日：2022-05-05
申请号：US17580295
申请日：2022-01-20
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, JR. , Ken Czerwinski , Bassem S. El-Dasher , Brian C. Kelleher , William M. Kerlin , Kevin Kramer , Jeffery F. Latkowski , Robert C. Petroski , Joshua C. Walter
IPC分类号： G21C3/54
摘要： An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active “protecting isotopes” (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes.
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公开(公告)号：US11276503B2
公开(公告)日：2022-03-15
申请号：US16676183
申请日：2019-11-06
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, Jr. , Ken Czerwinski , Bassem S. El-Dasher , Brian C. Kelleher , William M. Kerlin , Kevin Kramer , Jeffery F. Latkowski , Robert C. Petroski , Joshua C. Walter
摘要： An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active “protecting isotopes” (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes.
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