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公开(公告)号：US20240312649A1
公开(公告)日：2024-09-19
申请号：US18350970
申请日：2023-07-12
发明人： Rei KIMURA , Kazuhito ASANO
IPC分类号： G21C5/12 , G21C3/52 , G21C7/26 , G21C15/247
CPC分类号： G21C5/12 , G21C3/52 , G21C7/26 , G21C15/247
摘要： A nuclear reactor comprising: a moderator including a metal hydride; and a nuclear fuel in which europium is added as an additive to a main nuclear fuel material. Thus, the nuclear reactor can be kept in the subcritical state even under the state where all the control devices are pulled out before startup.
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公开(公告)号：US20240079153A1
公开(公告)日：2024-03-07
申请号：US18262621
申请日：2022-01-17
申请人： BAE SYSTEMS plc
发明人： Jeremy Henry Owston
摘要： A thermal bridge for improving thermal transfer between a fuel element to a fuel block wherein there is provided a high temperature gas cooled nuclear reactor fuel block comprising a fuel channel and a coolant channel wherein the fuel channel comprises a fuel element, the fuel channel further comprising a thermal bridge thermally linking the fuel element and the fuel channel, wherein the thermal bridge comprises a melting point greater than the working temperature of the fuel block, thereby improving thermal transfer from the fuel element to the fuel block, thereby improving thermal transfer to the coolant channel.
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公开(公告)号：US11728044B2
公开(公告)日：2023-08-15
申请号：US17399822
申请日：2021-08-11
发明人： Eric A. Barringer , Russell R. Jensen , Jeremy L. Gustafson , Matt Ales , Joshua J. Bergman , Ryan T. Swanson , Jonathan K. Witter , Danny Galicki , James B. Inman , Matt Krecicki , Roger Ridgeway
摘要： Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. Continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. A fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.
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公开(公告)号：US20230211898A1
公开(公告)日：2023-07-06
申请号：US18008831
申请日：2021-08-17
发明人： Michael John Eades
摘要： Combined moderator-propellant technologies allow a dual-purpose fluid to act as both a nuclear moderator as well as a propellant in a nuclear reactor system, such as a nuclear thermal propulsion (NTP) system. By increasing the mass efficiency of the NTP system and improving the overall performance during operation, the combined moderator-propellant technologies improve valuable payload efficiency in the NTP system. Advantageously, the combined moderator-propellant technologies require little to no dedicated storage space for the majority of NTP system operation. For example, the combined moderator-propellant is ammonia (NH3), which satisfies moderation requirements as well as propulsion requirements for the NTP system.
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公开(公告)号：US20220148744A1
公开(公告)日：2022-05-12
申请号：US17522678
申请日：2021-11-09
发明人： Doug Bernauer
摘要： A compact nuclear reactor system can include a set of nuclear reactor each including: a moderating body; a heat pipe disposed within the moderating body and arranged substantially parallel to the longitudinal axis; nuclear fuel arranged within the moderating body and configured to heat a working fluid passable through the heat pipe; and a neutron moderator arranged within the moderating body and configured to slow a rate of fission within the moderating body. The compact nuclear reactor system can also include a control system including: a rotatable sleeve defining a first portion including a neutron poison material; and a second portion including a neutron transparent material. The compact nuclear reactor system can also include a drive system connected to the sleeve and configured to rotate the sleeve about the sleeve axis to control neutron flux between the set of nuclear reactor cores.
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公开(公告)号：US20220013243A1
公开(公告)日：2022-01-13
申请号：US16926132
申请日：2020-07-10
摘要： Provided herein is a moderation module and a thermal neutron micro-reactor.
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公开(公告)号：US10748670B1
公开(公告)日：2020-08-18
申请号：US16517096
申请日：2019-07-19
申请人： Texas Thorium , LLC
摘要： A Thorium molten salt energy system is disclosed that includes a proton beam source for producing a proton beam, that can vary between a first energy level and a second energy level of, where the generated proton bean can be directed into a main assembly containing both Thorium-containing molten salt and Thorium fuel rods, each containing an inner Beryllium element and an outer solid Thorium element. The generated proton beam can be shaped and directed to impinge upon Lithium within the molten salt to promote the generation of thermal neutrons and the fission of Uranium within the molten salt. The generated proton beam can also be shaped and directed to impinge upon the Beryllium within the Thorium fuel rods to promote the generation of high energy neutrons.
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公开(公告)号：US20200027587A1
公开(公告)日：2020-01-23
申请号：US16254019
申请日：2019-01-22
发明人： Francesco VENNERI
摘要： A composite moderator medium for nuclear reactor systems and a method of fabricating a composite moderator block formed of the composite moderator medium. The composite moderator medium includes two or more moderators, such as a low moderating material and a high moderating material. The high moderating material has a higher neutron slowing down power compared to the low moderating material. The low moderating material includes a moderating matrix of silicon carbide or magnesium oxide. The high moderating material is dispersed within the moderating matrix and includes beryllium, boron, or a compound thereof. The high moderating material is encapsulated within the low moderating material such that the high moderating material is not exposed outside of the low moderating material. The method can include selecting a sintering aid and a weight percent of the sintering aid in a composite moderator mixture based on the low moderating material and spark plasma sintering.
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公开(公告)号：US20190108920A1
公开(公告)日：2019-04-11
申请号：US15834922
申请日：2017-12-07
申请人： HOWE INDUSTRIES, LLC
发明人： TROY M. HOWE , STEVEN D. HOWE
摘要： A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.
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公开(公告)号：US20170349496A1
公开(公告)日：2017-12-07
申请号：US15538375
申请日：2015-12-17
申请人： IBIDEN CO., LTD.
发明人： Takashi TAKAGI , Masahiro YASUDA
CPC分类号： C04B35/80 , C04B35/571 , C04B35/806 , C23C16/045 , C23C16/325 , C23C16/42 , C23C16/44 , G21C1/07 , G21C5/12 , G21C5/16 , G21C11/06 , G21C21/00 , Y02E30/36
摘要： A nuclear reactor structure configuring a pebble accommodating space of a pebble bed type nuclear reactor includes a core material including graphite and a ceramic/ceramic composition material covering a surface of the core material. According to a core material processing step (A) of processing the core material including graphite into a quadrangular prism, a bottom surface of which is an approximately isosceles trapezoid, a step (B) of obtaining a base material by covering the core material with an aggregate including a ceramic fiber, and a CVD step (C) of putting the base material into a CVD reactor and forming a SiC matrix in gaps of the aggregate, thereby forming a ceramic/ceramic composite material on a surface of the core material, the nuclear reactor structure capable of enhancing durability, preventing cracking, etc. from occurring, and preventing exposure of graphite as the core material from occurring, can be provided.
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