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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：US5015437A
公开(公告)日：1991-05-14
申请号：US437947
申请日：1989-11-17
申请人： Hans K. Fauske , George H. Clare
发明人： Hans K. Fauske , George H. Clare
摘要： A reactor core for a gas-cooled reactor, which core is composed of a plurality of prismatic bodies (2) of graphite containing nuclear fuel and having a top wall, a bottom wall and a plurality of vertically extending side walls, each graphite body (2) being provided with a plurality of first coolant flow channels (4) extending vertically between the top wall and the bottom wall, and with a plurality of second coolant flow channels (6) extending transversely to the first channels (4) and each interconnecting a plurality of the first channels (4).
摘要翻译： 一种用于气冷反应堆的反应堆芯，该芯由多个含有核燃料的石墨的棱柱体（2）组成，并具有顶壁，底壁和多个垂直延伸的侧壁，每个石墨体 2）设置有在顶壁和底壁之间垂直延伸的多个第一冷却剂流动通道（4），以及横向于第一通道（4）延伸的多个第二冷却剂流动通道（6），并且每个互连 多个第一通道（4）。
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公开(公告)号：US4393510A
公开(公告)日：1983-07-12
申请号：US701806
申请日：1976-07-01
申请人： Linton W. Lang , Robert L. Stetson
发明人： Linton W. Lang , Robert L. Stetson
摘要： The production of a novel nuclear fuel utilizing clean uranium 233 in combination with other nuclear materials is made possible by utilization of an equally novel reactor configuration and method of operation. Clean uranium 233 is produced from thorium in a light water reactor while utilizing discrete separation of the thorium being irradiated from the fissile fuel. This clean uranium 233 is then incorporated directly as fissile isotope enrichment into a new nuclear fuel which may be done without encountering the usual difficulties and hazards in the handling of uranium 233 or the expense and delays associated with gaseous diffusion enrichment. The thorium from this process may be directly reprocessed for reactor charging without radiation hazard also.
摘要翻译： 通过利用同样新颖的反应器构造和操作方法，可以利用利用清洁铀233与其它核材料组合的新型核燃料的生产。 清洁铀233在轻水反应堆中由钍生产，同时利用从易裂变燃料照射的钍的离散分离。 然后，这种干净的铀233直接作为裂变同位素浓缩结合到新的核燃料中，可以在不遇到处理铀233或与气体扩散富集相关的费用和延误方面遇到的常见困难和危险的情况下进行。 来自该过程的钍可以直接再加工用于反应器充电而没有辐射危害。
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公开(公告)号：US3891502A
公开(公告)日：1975-06-24
申请号：US27705072
申请日：1972-08-01
申请人： NUKEM GMBH
摘要： Block fuel elements for high temperature power reactors that can be reprocessed simply are prepared in which the feed and breed zones are connected with the graphite matrix directly and without transition. They are disposed separately from each other in such a manner that the feed zones and the breed zones can be separately removed one after the other from the structural graphite. In the reprocessing operation there are recovered uranium 233 from the breed particles, uranium 235 and fission products from the feed particles.
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公开(公告)号：US2967811A
公开(公告)日：1961-01-10
申请号：US21660751
申请日：1951-03-20
申请人： OLIVER FLINT
发明人： OLIVER FLINT
CPC分类号： G21C3/04 , G21C3/22 , Y02E30/40 , Y10S376/903
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公开(公告)号：US11942229B2
公开(公告)日：2024-03-26
申请号：US16851142
申请日：2020-04-17
发明人： Craig D. Gramlich
摘要： Fission reactor has a cladding encasing a heat generating source including a fissionable nuclear fuel composition. The heat generating source is offset from the surface of the cladding and molten metal is located within the void space formed by the offset. As a liquid, the molten metal will flow and occupy any contiguous network of void space within the fuel cavity and provides thermal transfer contact between the heat generating source and the cladding. The cladding separates the heat generating source and the molten metal from the primary coolant volume.
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公开(公告)号：US11551822B2
公开(公告)日：2023-01-10
申请号：US17473433
申请日：2021-09-13
发明人： Edward J. Lahoda , Peng Xu , Robert L. Oelrich, Jr. , Hemant Shah , Jonathan Wright , Lu Cai
摘要： A method of forming a water resistant boundary on a fissile material for use in a water cooled nuclear reactor is described. The method comprises mixing a powdered fissile material selected from the group consisting of UN and U3Si2 with an additive selected from oxidation resistant materials having a melting or softening point lower than the sintering temperature of the fissile material, pressing the mixed fissile and additive materials into a pellet, sintering the pellet to a temperature greater than the melting point of the additive. Alternatively, if the melting point of the oxidation resistant particles is greater than the sintering temperature of UN or U3Si2, then the oxidation resistant particles can have a particle size distribution less than that of the UN or U3Si2.
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公开(公告)号：US20200373024A1
公开(公告)日：2020-11-26
申请号：US16851142
申请日：2020-04-17
发明人： Craig D. GRAMLICH
摘要： Fission reactor has a cladding encasing a heat generating source including a fissionable nuclear fuel composition. The heat generating source is offset from the surface of the cladding and molten metal is located within the void space formed by the offset. As a liquid, the molten metal will flow and occupy any contiguous network of void space within the fuel cavity and provides thermal transfer contact between the heat generating source and the cladding. The cladding separates the heat generating source and the molten metal from the primary coolant volume.
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公开(公告)号：US10276271B2
公开(公告)日：2019-04-30
申请号：US14770894
申请日：2014-03-26
IPC分类号： G21C1/02 , G21C15/257 , G21C1/32 , G21C3/04 , G21C3/22 , G21C7/08 , G21C11/06 , G21C15/04 , G21D5/02 , G21H1/00 , G21H3/00 , G21C3/08 , G21C3/40
摘要： Embodiments of the present invention pertain to a power system utilizing a uranium-based reactor for space missions. For example, the power system may include a reactor configured to generate thermal energy using a uranium core. A plurality of heat pipes may be configured to transfer thermal energy from the reactor core to a plurality of Stirling engines to generate electricity for a spacecraft.
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公开(公告)号：US4001079A
公开(公告)日：1977-01-04
申请号：US605371
申请日：1975-08-15
申请人： John A. Rylatt
发明人： John A. Rylatt
IPC分类号： G21C1/02 , G21C13/028 , G21C3/22
CPC分类号： G21C13/028 , G21C1/02 , Y02E30/34
摘要： A liquid-metal-cooled fast-breeder reactor includes a bridge structure for separating hot outlet coolant from relatively cool inlet coolant consisting of an annular stainless steel baffle plate extending between the core barrel surrounding the core and the thermal liner associated with the reactor vessel and resting on ledges thereon, there being inner and outer circumferential webs on the lower surface of the baffle plate and radial webs extending between the circumferential webs, a stainless steel insulating plate completely covering the upper surface of the baffle plate and flex seals between the baffle plate and the ledges on which the baffle plate rests to prevent coolant from washing through the gaps therebetween. The baffle plate is keyed to the core barrel for movement therewith and floating with respect to the thermal liner and reactor vessel.
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