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1. 发明授权

US12087459B2 Closed-vessel molten salt fission reactor 有权
公开(公告)号：US12087459B2
公开(公告)日：2024-09-10
申请号：US18120691
申请日：2023-03-13
申请人： BK Clean Energy LLC
发明人： Harry L. Bregman , Gregory F. Kushnir
IPC分类号： G21C7/30 , G21C1/22 , G21C5/02 , G21C7/26 , G21C3/54 , G21C15/04 , G21F5/06
CPC分类号： G21C7/30 , G21C1/22 , G21C5/02 , G21C7/26 , G21C3/54 , G21C15/04 , G21F5/065
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 container is rotatable between different orientations. The container may be hollow and a solution of fissile materials and salt materials may be provided within the 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 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.

2. 发明公开

US20230411025A1 CLOSED-VESSEL MOLTEN SALT FISSION REACTOR 审中-公开
公开(公告)号：US20230411025A1
公开(公告)日：2023-12-21
申请号：US18120691
申请日：2023-03-13
申请人： BK Clean Energy LLC
发明人： Harry L. Bregman , Geogory F. Kushnir
IPC分类号： G21C7/30 , G21C1/22 , G21C5/02 , G21C7/26
CPC分类号： G21C7/30 , G21C1/22 , G21C5/02 , G21C7/26 , G21C3/54
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.

3. 发明授权

US10008294B2 Methods and systems for migrating fuel assemblies in a nuclear fission reactor 有权
公开(公告)号：US10008294B2
公开(公告)日：2018-06-26
申请号：US12590448
申请日：2009-11-06
申请人： Roderick A. Hyde , Robert C Petroski , Joshua C. Walter , Thomas Allan Weaver , Charles Whitmer , Lowell L. Wood, Jr. , George B. Zimmerman , Ehud Greenspan
发明人： Roderick A. Hyde , Robert C Petroski , Joshua C. Walter , Thomas Allan Weaver , Charles Whitmer , Lowell L. Wood, Jr. , George B. Zimmerman , Ehud Greenspan
IPC分类号： G21C7/00 , G21C1/02 , G21C7/30 , G21C17/108 , G21D3/00
CPC分类号： G21C7/005 , G21C1/026 , G21C7/30 , G21C17/108 , G21D3/001 , Y02E30/34 , Y02E30/39
摘要： Illustrative embodiments provide methods and systems for migrating fuel assemblies in a nuclear fission reactor, methods of operating a nuclear fission traveling wave reactor, methods of controlling a nuclear fission traveling wave reactor, systems for controlling a nuclear fission traveling wave reactor, computer software program products for controlling a nuclear fission traveling wave reactor, and nuclear fission traveling wave reactors with systems for migrating fuel assemblies.

4. 发明申请

US20170301413A1 NUCLEAR FUEL SALTS 审中-公开
公开(公告)号：US20170301413A1
公开(公告)日：2017-10-19
申请号：US15584926
申请日：2017-05-02
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： G21C1/03 , G21C19/303 , G21C7/30 , G21C1/22 , G21C3/54 , G21C3/22 , G21C19/50 , G21C15/28
CPC分类号： G21C1/03 , G21C1/22 , G21C3/22 , G21C3/54 , G21C7/30 , G21C15/28 , G21C19/28 , G21C19/303 , G21C19/307 , G21C19/50 , Y02E30/34 , Y02E30/35 , Y02E30/38 , Y02E30/39
摘要： This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UClxFy are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.

5. 发明授权

US4609522A Mechanical drive system for moving fuel 失效
标题翻译：用于移动燃料的机械驱动系统
公开(公告)号：US4609522A
公开(公告)日：1986-09-02
申请号：US576677
申请日：1984-02-03
申请人： Albert C. Davidson , David E. Boyle
发明人： Albert C. Davidson , David E. Boyle
IPC分类号： G21C3/30 , G21C3/328 , G21C7/00 , G21C7/30
CPC分类号： G21C7/30 , Y02E30/39
摘要： A mechanical drive system (10) for moving alternate nuclear reactor fuel rods (14) within the nuclear reactor core (12) and relative to the remaining stationary nuclear reactor fuel rods (16) so as to axially displace the movable fuel rods (14), and enriched and natural uranium fuel zones defined therein, relative to similarly defined enriched and natural uranium fuel zones within the stationary fuel rods (16) in order to optimize utilization of excess or free neutrons produced within the nuclear reactor core within a fuel cycle. The nuclear reactor fuel rods (14, 16) all have a length which is less than that of standard-sized nuclear reactor fuel rods, and therefore, a plenum chamber (20) is able to be defined between an upper core plate (22) and an auxiliary upper core plate (24). A drive plate grid assembly (36, 38) is attached to the movable fuel rods (14), and hydraulic drive mechanisms (46) move the grid assembly (36, 38) and the movable fuel rods (14) so as to axially displace the fuel rods (14) relative to the stationary fuel rods (16) whereby the enriched and natural uranium fuel zones defined within the fuel rods (14, 16) optimally operationally interface throughout the fuel cycle. The movable fuel rods (14) are progressively moved during the fuel cycle such that at the beginning of the fuel cycle, the enriched and natural uranium fuel zones defined between adjacent fuel rods (14, 16) are mis-aligned, while at the end of the fuel cycle, the fuel zones are aligned in horizontal layers.
摘要翻译：一种机械驱动系统（10），用于在所述核反应堆堆芯（12）内并相对于所述剩余的固定核反应堆燃料棒（16）移动替代核反应堆燃料棒（14），以使所述可动燃料棒（14）轴向移动，，以及相对于固定燃料棒（16）内相似限定的富集和天然铀燃料区限定在其中的富集和天然铀燃料区，以便优化在燃料循环内在核反应堆核心内产生的过量或自由中子的利用。核反应堆燃料棒（14,16）的长度小于标准尺寸的核反应堆燃料棒的长度，因此，能够在上芯板（22）和辅助上芯板（24）。驱动板格栅组件（36,38）连接到可移动燃料棒（14）上，并且液压驱动机构（46）使格栅组件（36,38）和可移动燃料棒（14）移动以便轴向移位所述燃料棒（14）相对于所述固定燃料棒（16），由此在所述燃料棒（14,16）内限定的所述富集和天然的铀燃料区域在燃料循环周期中最佳地操作地接合。在燃料循环期间，可移动燃料棒（14）逐渐移动，使得在燃料循环开始时，在相邻的燃料棒（14,16）之间限定的富集和天然的铀燃料区域被错位排列，同时在最后燃料循环的燃料区域在水平层中对齐。

6. 发明授权

US4255236A Reactor and fuel assembly design for improved fuel utilization in liquid moderated thermal reactors 失效
标题翻译：反应器和燃料组件设计，用于改善液体温和热反应堆的燃料利用率
公开(公告)号：US4255236A
公开(公告)日：1981-03-10
申请号：US847524
申请日：1977-11-01
申请人： Thomas R. Robbins
发明人： Thomas R. Robbins
IPC分类号： G21C7/00 , G21C7/30 , G21C19/20
CPC分类号： G21C7/00 , G21C7/30 , G21Y2002/201 , G21Y2004/10 , G21Y2004/40 , Y02E30/39
摘要： An improved reactor and fuel assembly design is disclosed wherein a light water reactor is initially run with undermoderated fuel assemblies to take advantage of increased conversion ratio, and after a suitable period of operation, the neutron spectrum for the undermoderated assemblies is shifted to lower energies to increase reactivity by withdrawing a number of fuel rods from the assemblies. The increased reactivity allows for continued operation of the modified assembly, and the fuel rods which are removed are used to construct similar assemblies which are also capable of continued operation. The improved reactor and fuel assembly design results in improved fuel utilization and neutron economy and reduced control requirements for the reactor.
摘要翻译：公开了一种改进的反应器和燃料组件设计，其中轻水反应器最初使用未燃烧的燃料组件运行以利用增加的转化率，并且在适当的操作周期之后，未经偏转的组件的中子谱转移到较低的能量通过从组件中抽出多个燃料棒来增加反应性。增加的反应性允许改进的组件的继续操作，并且被去除的燃料棒用于构造也能够继续操作的类似的组件。改进的反应器和燃料组件设计可以改善燃料利用率和中子经济性，并降低反应堆的控制要求。

7. 发明授权

US3843765A Actinide nitride-fueled reactor and continuous method of operating the same 失效
标题翻译：氮氧化物燃料反应器和连续运行的方法
公开(公告)号：US3843765A
公开(公告)日：1974-10-22
申请号：US82565169
申请日：1969-05-19
申请人： PARLEE ANDERSON CORP
发明人： ANDERSON R , PARLEE N
IPC分类号： G21C1/22 , G21C7/30 , G21C19/30 , G21C19/50 , C01G43/00 , G21C19/28
CPC分类号： G21C1/22 , G21C7/30 , G21C19/30 , G21C19/50 , G21Y2002/201 , G21Y2002/601 , G21Y2004/30 , G21Y2004/302 , G21Y2004/402 , Y02E30/39
摘要： An actinide nitride-fueled nuclear reactor and a method of operation therefor, including continuous in situ removal of fission products and optional addition of fuel-forming actinide material as the reaction proceeds. The reactor employed has a fuel system comprising a critical mass of a nitride of an actinide metal in contact with a non-critical solution of the actinide metal in a molten metal solvent of low neutron adsorption cross section such as tin, said fuel system being maintained under a nitrogen atmosphere in an inert, refractory vessel such as graphite which is non-conducive to the formation of actinide oxides. Fission products formed are continuously exchanged with the actinide metal dissolved in the molten metal solvent as the nuclear reaction proceeds, with equivalent amounts of actinide nitride being formed and precipitated into the critical mass as fission products are dissolved in the molten metal solution. Temperature extrusions tend to be suppressed by the nitride decomposition which ensues as temperatures are increased without any balancing increase in nitrogen pressures to restore the equilibrium.

8. 发明授权

US3623946A Nuclear reactor 失效
公开(公告)号：US3623946A
公开(公告)日：1971-11-30
申请号：US3623946D
申请日：1965-06-22
申请人： ATOMIC ENERGY COMMISSION
发明人： HOBSON ROBERT R , GRIFFIN THOMAS E
IPC分类号： G21C7/28 , G21C7/30 , G21D7/04 , G21C7/00
CPC分类号： G21D7/04 , G21C7/28 , G21C7/30 , Y02E30/39 , Y10S376/909
摘要： A nuclear reactor comprising: AN ELONGATED CYLINDRICAL CORE LONGITUDINALLY DIVIDED INTO QUADRANTS, EACH CORE QUADRANT BEING NEUTRONICALLY SUBCRITICAL; MEANS FOR FLEXIBLY FASTENING TOGETHER TWO DIAMETRICALLY OPPOSED QUADRANTS AT ONE END OF SAID CORE AND FOR RETAINING THE REMAINING TWO QUADRANTS IN A FIXED POSITION; MEANS FOR DRIVING THE FREE ENDS OF SAID FLEXIBLY FASTENED QUADRANTS APART AND FOR RETURNING THEM TOGETHER; MEANS FOR CONTROLLING THE REACTIVITY OF SAID REACTOR CORE; AND, MEANS FOR REMOVING THE ENERGY GENERATED BY SAID REACTOR CORE.

9. 发明授权

US3276964A Segmented nuclear reactor core having pivotable outer control assemblies 失效
标题翻译：分段核反应堆堆芯具有可枢转的外部控制组件
公开(公告)号：US3276964A
公开(公告)日：1966-10-04
申请号：US3264860
申请日：1960-05-31
申请人： COMBUSTION ENG
发明人： WEST JOHN M , FRANK BEVILACQUA
IPC分类号： G21C1/08 , G21C7/30 , G21D3/12
CPC分类号： G21D3/12 , G21C1/08 , G21C7/30 , Y02E30/31 , Y02E30/39

10. 发明授权

US2872399A Self-reactivating neutron source for a neutronic reactor 失效
标题翻译：用于中子反应堆的自恢复中子源
公开(公告)号：US2872399A
公开(公告)日：1959-02-03
申请号：US36661553
申请日：1953-07-07
申请人： NEWSON HENRY W
发明人： NEWSON HENRY W
IPC分类号： G21C1/30 , G21C7/30 , G21C7/34
CPC分类号： G21C1/30 , G21C1/303 , G21C7/30 , G21C7/34 , Y02E30/39

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