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21. 发明授权

US4005178A Method for converting UF5 to UF4 in a molten fluoride salt 失效
标题翻译：在熔融氟化物盐中将UF5转化为UF4的方法
公开(公告)号：US4005178A
公开(公告)日：1977-01-25
申请号：US594823
申请日：1975-07-10
申请人： Melvin R. Bennett , Carlos E. Bamberger , A. Donald Kelmers
发明人： Melvin R. Bennett , Carlos E. Bamberger , A. Donald Kelmers
IPC分类号： C01G43/06 , G21C19/44 , G21C19/50 , B01J23/42 , B01J23/52
CPC分类号： G21C19/50
摘要： The reduction of UF.sub.5 to UF.sub.4 in a molten fluoride salt by sparging with hydrogen is catalyzed by metallic platinum. The reaction is also catalyzed by platinum alloyed with gold reaction equipment.
摘要翻译：通过用氢气喷射在熔融氟化物盐中将UF5还原成UF4由金属铂催化。该反应也由与金反应设备合金的铂催化。

22. 发明授权

US3310500A Distillation method for reprocessing molten salt reactor fuels 失效
标题翻译：用于后处理熔盐反应堆燃料的蒸馏方法
公开(公告)号：US3310500A
公开(公告)日：1967-03-21
申请号：US51047765
申请日：1965-11-29
申请人： KELLY MINTON J
发明人： KELLY MINTON J
IPC分类号： G21C19/50
CPC分类号： G21C19/50

23. 发明授权

US3130042A Processing thorium-bismuth and thorium-lead compounds 失效
标题翻译：加工钍铋和钍铅化合物
公开(公告)号：US3130042A
公开(公告)日：1964-04-21
申请号：US12882761
申请日：1961-08-02
申请人： DOW CHEMICAL CO
发明人： TEITEL ROBERT J
IPC分类号： C22B60/02 , G21C19/50
CPC分类号： C22B60/0291 , G21C19/50

24. 发明授权

US3110555A Separation of protactinium from molten salt reactor fuel compositions 失效
标题翻译：从熔盐反应堆燃料组合物中分离prot。
公开(公告)号：US3110555A
公开(公告)日：1963-11-12
申请号：US5124260
申请日：1960-08-22
申请人： SHAFFER JAMES H , STRAIN JAMES E , CUNEO DAVID R , KELLY MINTON J
发明人： SHAFFER JAMES H , STRAIN JAMES E , CUNEO DAVID R , KELLY MINTON J
IPC分类号： C01G99/00 , C22B60/02 , G21C19/50
CPC分类号： C01G99/006 , C22B60/0213 , C22B60/0291 , C22B60/0295 , G21C19/50 , Y02P10/212

25. 发明授权

US2758023A Method of purifying liquid fuels of nuclear reactors 失效
标题翻译：净化核反应堆液体燃料的方法
公开(公告)号：US2758023A
公开(公告)日：1956-08-07
申请号：US35091053
申请日：1953-04-24
申请人： BAREIS DAVID W
发明人： BAREIS DAVID W
IPC分类号： G21C19/50
CPC分类号： G21C19/50

26. 发明授权

US11211176B2 Continuous reprocessing of spent nuclear fuel 有权
公开(公告)号：US11211176B2
公开(公告)日：2021-12-28
申请号：US16965329
申请日：2019-01-30
申请人： Ian Richard Scott
发明人： Ian Richard Scott
IPC分类号： G21C19/50 , C25C3/34 , C25C3/36 , C25C7/00 , G21C19/48
摘要： Spent nuclear fuel is added to an electro-reduction cell, wherein the electro-reduction cell includes a halide salt electrolyte, and anode, and a cathode including an alloy of uranium and a first metal forming a low melting point alloy with uranium, the first metal being one or more of: iron; chromium; nickel; manganese; and cobalt. The spent nuclear fuel is electrochemically reduced at a potential sufficient to reduce plutonium and lanthanides in the spent nuclear fuel, to form a molten alloy of the first metal, uranium and higher actinides present in the spent nuclear fuel. The alloy is extracted from the electro-reduction cell while uranium oxide is present in the electro-reduction cell. The spent nuclear fuel includes uranium oxide and at least 1 mol of lanthanides per tonne of uranium in the spent nuclear fuel, and the electro-reduction cell is operated at a temperature above the melting point of the alloy.

27. 发明授权

US11170901B2 Fission reaction control in a molten salt reactor 有权
公开(公告)号：US11170901B2
公开(公告)日：2021-11-09
申请号：US16595064
申请日：2019-10-07
申请人： TerraPower, LLC
发明人： Jesse R. Cheatham, III , Anselmo T. Cisneros, Jr. , Jeffery F. Latkowski , James M. Vollmer , Christopher J. Johns
IPC分类号： G21C19/28 , G21C7/30 , G21C1/22 , G21C3/24 , G21C1/03 , G21C3/54 , G21C15/28 , G21C19/30 , G21C19/50 , G21C19/303 , G21C19/20 , G21C17/104 , G21C3/22
摘要： A molten salt reactor includes a nuclear reactor core for sustaining a nuclear fission reaction fueled by a molten fuel salt. A molten fuel salt control system removes a volume of the molten fuel salt from the nuclear reactor core to maintain a reactivity parameter within a range of nominal reactivity. The molten fuel salt control system includes a molten fuel salt exchange system that fluidically couples to the nuclear reactor core and exchanges a volume of the molten fuel salt with a volume of a feed material containing a mixture of a selected fertile material and a carrier salt. The molten fuel salt control system can include a volumetric displacement control system having one or more volumetric displacement bodies insertable into the nuclear reactor core. Each volumetric displacement body can remove a volume of molten fuel salt from the nuclear reactor core, such as via a spill-over system.

28. 发明授权

US10438705B2 Fission reaction control in a molten salt reactor 有权
公开(公告)号：US10438705B2
公开(公告)日：2019-10-08
申请号：US14981606
申请日：2015-12-28
申请人： TerraPower, LLC
发明人： Jesse R. Cheatham, III , Anselmo T. Cisneros, Jr. , Jeffery F. Latkowski , James M. Vollmer , Christopher J. Johns
IPC分类号： G21C7/30 , G21C1/22 , G21C3/24 , G21C15/28 , G21C19/30 , G21C19/50 , G21C19/303 , G21C1/03 , G21C3/54 , G21C19/28 , G21C19/20 , G21C17/104 , G21C3/22
摘要： A molten salt reactor includes a nuclear reactor core for sustaining a nuclear fission reaction fueled by a molten fuel salt. A molten fuel salt control system removes a volume of the molten fuel salt from the nuclear reactor core to maintain a reactivity parameter within a range of nominal reactivity. The molten fuel salt control system includes a molten fuel salt exchange system that fluidically couples to the nuclear reactor core and exchanges a volume of the molten fuel salt with a volume of a feed material containing a mixture of a selected fertile material and a carrier salt. The molten fuel salt control system can include a volumetric displacement control system having one or more volumetric displacement bodies insertable into the nuclear reactor core. Each volumetric displacement body can remove a volume of molten fuel salt from the nuclear reactor core, such as via a spill-over system.

29. 发明授权

US08942338B2 Traveling wave nuclear fission reactor, fuel assembly, and method of controlling burnup therein 有权
标题翻译：旅行波核裂变反应堆，燃料组装及其中的燃耗控制方法
公开(公告)号：US08942338B2
公开(公告)日：2015-01-27
申请号：US12384669
申请日：2009-04-06
申请人： Charles E. Ahlfeld , John Rogers Gilleland , Roderick A. Hyde , Muriel Y. Ishikawa , David G. McAlees , Nathan P. Myhrvold , Charles Whitmer , Lowell L. Wood, Jr. , George B. Zimmerman
发明人： Charles E. Ahlfeld , John Rogers Gilleland , Roderick A. Hyde , Muriel Y. Ishikawa , David G. McAlees , Nathan P. Myhrvold , Charles Whitmer , Lowell L. Wood, Jr. , George B. Zimmerman
IPC分类号： G21C7/06 , G21C1/02 , G21C5/20 , G21C19/50 , G21C3/07
CPC分类号： G21C7/06 , G21C1/022 , G21C1/024 , G21C1/026 , G21C3/07 , G21C5/20 , G21C19/50 , Y02E30/34 , Y02E30/39
摘要： A traveling wave nuclear fission reactor, fuel assembly, and a method of controlling burnup therein. In a traveling wave nuclear fission reactor, a nuclear fission reactor fuel assembly comprises a plurality of nuclear fission fuel rods that are exposed to a deflagration wave burnfront that, in turn, travels through the fuel rods. The excess reactivity is controlled by a plurality of movable neutron absorber structures that are selectively inserted into and withdrawn from the fuel assembly in order to control the excess reactivity and thus the location, speed and shape of the burnfront. Controlling location, speed and shape of the burnfront manages neutron fluence seen by fuel assembly structural materials in order to reduce risk of temperature and irradiation damage to the structural materials.
摘要翻译：行波核裂变反应堆，燃料组件及其中的燃料控制方法。在行波核裂变反应堆中，核裂变反应堆燃料组件包括多个核裂变燃料棒，这些核裂变燃料棒暴露于爆燃波燃烧前沿，而爆燃波燃烧棒又穿过燃料棒。多余的反应性由多个可移动的中子吸收体结构控制，这些结构被选择性地插入到燃料组件中并从燃料组件中排出，以便控制燃烧前沿的过量反应性和位置，速度和形状。控制燃烧的位置，速度和形状管理燃料组装结构材料所看到的中子通量，以减少对结构材料的温度和辐照损害的风险。

30. 发明授权

US4686089A Sieve-plate column for counterflow extraction 失效
标题翻译：用于逆流萃取的筛板塔
公开(公告)号：US4686089A
公开(公告)日：1987-08-11
申请号：US833356
申请日：1986-02-25
申请人： Karlheinz Haberland
发明人： Karlheinz Haberland
IPC分类号： G21C19/46 , B01D11/04 , G21C19/42 , G21F9/06 , G21C19/50 , G21F9/20
CPC分类号： B01D11/043 , G21C19/42
摘要： The invention relates to a sieve-plate column for liquid-liquid counterflow extraction of two phases which are of different weights and which are not soluble one in the other. A mixing arrangement is disposed between two sieve plates. In order to further increase cross-mixing of the phases and thus the material exchange thereof with a good rate of through-put, a static mixing element is arranged between each two sieve plates. Static mixing elements generally have, over their entire cross-section, a plurality of open channels which are arranged adjacent to each other and which extend inclinedly with respect to the direction of flow, the upper opening and the lower opening of each channel thereby being displaced radially relative to each other.
摘要翻译：本发明涉及一种用于液 - 液逆流萃取的筛板塔，它是不同重量的两相不相溶的两相。混合装置设置在两个筛板之间。为了进一步增加相的交叉混合，并因此以良好的通过率进行材料交换，在每个两个筛板之间设置静态混合元件。静态混合元件在其整个横截面上通常具有多个彼此相邻布置并且相对于流动方向倾斜地延伸的开放通道，每个通道的上部开口和下部开口被移位径向相对于彼此。

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