-
21.发明授权公开(公告)号：US11887741B2
公开(公告)日：2024-01-30
申请号：US17577680
申请日：2022-01-18
发明人： Jason B Ingraham , Gerald D. Kvaall, Jr. , Paul E. Cantonwine , Michael W. Thomas , William C. Cline
摘要： The fuel assembly includes at least one fuel rod and an outer channel with four sidewalls surrounding the fuel rod, the outer channel having a configuration based on a position of the fuel assembly within a core of the nuclear reactor, wherein at least a first select sidewall, of the four sidewalls of the outer channel, is a reinforced sidewall, the remaining sidewalls of the outer channel, other than the at least a first select sidewall, are non-reinforced sidewalls, the at least a first select sidewall being in a controlled location that faces and is directly adjacent to a control blade that is to be utilized in the nuclear reactor, wherein an entirety of the reinforced sidewall as a whole is at least one of thicker and made from a material that is more resistant to radiation-induced deformation as compared to an entirety of the non-reinforced sidewalls.
-
公开(公告)号：US11742095B2
公开(公告)日：2023-08-29
申请号：US17163558
申请日：2021-01-31
发明人： Gregory J. Pearson , Atul A. Karve
CPC分类号： G21C3/326 , G21C19/205 , Y02E30/30
摘要： Cores include different types of control cells in different numbers and positions. A periphery of the core just inside the perimeter may have higher reactivity fuel in outer control cells, and lower reactivity cells may be placed in an inner core inside the inner ring. Cores can include about half fresh fuel positioned in higher proportions in the inner ring and away from inner control cells. Cores are compatible with multiple core control cell setups, including BWRs, ESBWRs, ABWRs, etc. Cores can be loaded during conventional outages. Cores can be operated with control elements in only the inner ring control cells for reactivity adjustment. Control elements in outer control cells need be moved only at sequence exchanges. Near end of cycle, reactivity in the core may be controlled with inner control cells alone, and control elements in outer control cells can be fully withdrawn.
-
23.发明授权公开(公告)号：US10176899B2
公开(公告)日：2019-01-08
申请号：US13603184
申请日：2012-09-04
申请人： Kathryn M. Martin
发明人： Kathryn M. Martin
摘要： Nuclear fuel spacers include a deflection-limited elastic rod contact. Spacers may additionally include a rigid contact without elastic functionality. A degree of deflection may be chosen based on plastic deformation threshold, maximum fuel rod movement, anticipated transverse loads related to fuel assembly, inspection, handling, transportation, operation, accidents, and/or any other operating characteristic. Spacers include deflection-limited elastic contacts and/or rigid contacts in several arrangements within the spacer and/or on a single fuel rod. Spacers are compatible with a simple fabrication method that forms rigid, deflection-limiting, and elastic components from a single substrate. Nuclear fuel spacers are useable with several fuel assembly types.
-
公开(公告)号：US20170178755A9
公开(公告)日：2017-06-22
申请号：US13786438
申请日：2013-03-05
发明人： Kevin L. Ledford , Yuk-Chiu Lau , David W. White , Yang-Pi Lin , Paul E. Cantonwine , Nicholas R. Gullette , Timothy W. Clark
IPC分类号： G21C3/07
CPC分类号： G21C3/07 , C23C24/04 , G21C21/02 , G21Y2002/101 , G21Y2004/20 , Y02E30/40
摘要： Nuclear reactor components are treated with thermal methods to increase wear resistance. Example treatments include thermal treatments using particulate or powderized materials to form a coating. Methods can use cold spray, with low heat and high velocities to blast particles on the surface. The particles impact and mechanically deform, forming an interlocking coating with the surface and each other without melting or chemically reacting. Materials in the particles and resultant coatings include metallic alloys, ceramics, and/or metal oxides. Nuclear reactor components usable with methods of increased wear resistance include nuclear fuel rods and assemblies containing the same. Coatings may be formed on any desired surface, including fuel rod positions where spacer contact and fretting is most likely.
-
25.发明授权Method and system for designing a nuclear reactor core for uprated power operations 有权用于设计用于升级电力运行的核反应堆堆芯的方法和系统公开(公告)号：US09047995B2
公开(公告)日：2015-06-02
申请号：US11585965
申请日：2006-10-25
CPC分类号： G21D3/001 , G21C5/02 , G21C7/00 , G21Y2002/201 , G21Y2002/304 , G21Y2004/30 , G21Y2004/40 , Y02E30/39
摘要： In a method of designing a nuclear reactor core for uprated power operations, a set of constraints are inputted to be satisfied for uprated power operations, and a test reactor core design is generated based on the constraints. One or more automated tools may be selected from a set of automated tools to evaluate the test core design against the constraints. The selected tool may then be operated. Operation of the selected automated tool includes simulating reactor operation with the test core design, based on the constraints, to produce a plurality of outputs, comparing the outputs against the constraints, and providing data indicating constraints that were violated by the test core design during the simulation, based on the comparison. One or more of the automated tools are iterated until a test core design meets all constraints for uprated power operations, thereby representing an acceptable power uprate core design.
摘要翻译： 在设计用于上升功率操作的核反应堆堆芯的方法中，输入一组约束以满足上升功率操作，并且基于约束产生测试反应堆堆芯设计。 可以从一组自动化工具中选择一个或多个自动化工具，以根据约束来评估测试核心设计。 然后可以操作所选择的工具。 所选择的自动化工具的操作包括基于约束来模拟具有测试核心设计的反应堆操作，以产生多个输出，将输出与约束进行比较，以及提供指示在测试核心设计期间违反的约束的数据 仿真，基于比较。 一个或多个自动化工具被迭代，直到测试核心设计满足上升功率操作的所有约束，从而表示可接受的上电核心设计。
-
26.发明授权Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria 有权用于设计满足许可标准的核反应堆核心的计算机实现方法和系统公开(公告)号：US08873698B2
公开(公告)日：2014-10-28
申请号：US11642871
申请日：2006-12-21
IPC分类号： G06F17/50 , G06G7/54 , G21D3/00 , G21C19/20 , G21C17/00 , G21D3/04 , G21D3/08 , G06F17/00 , G06G7/00
CPC分类号： G21C17/00 , G21C19/205 , G21D3/001 , G21D3/04 , G21D3/08 , G21D2003/002 , G21Y2002/201 , G21Y2002/202 , G21Y2002/203 , G21Y2002/304 , G21Y2004/40 , G21Y2004/403 , Y02E30/39
摘要： In a computer-implemented method of designing a nuclear reactor of a given reactor plant, an initial, test reactor core design is generated for the given plant based on a plurality of limits input by a user. The limits include a plurality of transient licensing constraints to be satisfied for operating the given plant. The method includes selecting, from a set of automated tools, one or more automated tools to evaluate the test core design, and operating one of more of selected automated tools to output data for display to the user. The displayed data is related to a core design that satisfies the limits inclusive of the transient licensing constraints.
摘要翻译： 在设计给定反应堆设备的核反应堆的计算机实现的方法中，基于由用户输入的多个限制，为给定设备产生初始的测试反应堆核心设计。 这些限制包括要为运行给定设备而满足的许多暂时许可限制。 该方法包括从一组自动化工具中选择一个或多个自动化工具来评估测试核心设计，以及操作多个所选择的自动化工具之一来输出用于显示给用户的数据。 显示的数据与满足临时许可限制的限制的核心设计相关。
-
公开(公告)号：US08611488B2
公开(公告)日：2013-12-17
申请号：US13026940
申请日：2011-02-14
IPC分类号： G21C19/42
CPC分类号： G21C3/3206 , G21C3/30 , G21C3/3305 , Y02E30/40
摘要： A debris exclusion and retention device traps and retains foreign material within the lower tie plate of the fuel assembly utilizing the existing flow paths within the lower tie plate, and without redirecting coolant flow. Flow through the inlet nozzle of the lower tie plate into an enlarged lower tie plate housing creates strong jet impingement against the center of the lower tie plate grid or debris filter, if present, which has a tendency to push debris to the periphery of the lower tie plate. Low flow zones around the periphery of the lower tie plate allow debris to fall back toward the inlet nozzle. The retention device traps and retains debris in these low flow zones without impacting existing flow patterns in the lower tie plate. Thus, the retention device has minimal or no impact on lower tie plate pressure drop.
摘要翻译： 碎片排除和保持装置利用现有的下连接板内的流动路径捕集并且将异物留在燃料组件的下连接板内，并且不改变冷却剂流。 通过下连接板的入口喷嘴流入扩大的下连接板壳体会产生较强的喷射冲击，抵抗下连接板网格或碎屑过滤器的中心（如果存在），其倾向于将碎屑推到下部 领带。 围绕下连接板周边的低流动区允许碎屑向入口喷嘴回落。 保持装置在这些低流动区域中捕获和保留碎屑，而不会影响下连接板中的现有流动模式。 因此，保持装置对较低的连接板压降具有最小或没有影响。
-
公开(公告)号：US08565367B2
公开(公告)日：2013-10-22
申请号：US12078904
申请日：2008-04-08
申请人： Daniel Reese Lutz
发明人： Daniel Reese Lutz
IPC分类号： G21C3/34
摘要： Example embodiments are directed to fuel assembly components and nuclear fuel bundles including the fuel assembly components. Example embodiments of a fuel assembly component may include a cylindrical device having first and second ends and a mounting assembly on the first end of the cylindrical device configured to attach to and detach from a partial length fuel rod. Example embodiments of a nuclear fuel bundle may include an upper tie plate, a lower tie plate, at least one full-length fuel rod, at least one partial length fuel rod, and a fuel assembly component.
-
公开(公告)号：US08559586B2
公开(公告)日：2013-10-15
申请号：US10748174
申请日：2003-12-31
申请人： Lukas Trosman , Cary L. Kunz , Russell E. Stachowski , Russell M. Fawcett , Shingo Fujimaki , Daisuke Goto
发明人： Lukas Trosman , Cary L. Kunz , Russell E. Stachowski , Russell M. Fawcett , Shingo Fujimaki , Daisuke Goto
IPC分类号： G21C3/32
CPC分类号： G21C3/322 , G21C3/328 , G21Y2002/50 , G21Y2004/302 , Y02E30/31 , Y02E30/38
摘要： A reactor fuel bundle includes both full-length fuel rods and part-length fuel rods. The part-length rods are clumped in two groups—a first rod group surrounds one or more water passages which are generally centrally disposed in a channel of the fuel bundle, and a second rod group is distributed about an inner perimeter wall of the channel.
摘要翻译： 反应堆燃料束包括全长燃料棒和部分长度的燃料棒。 部分长度的杆被分成两组 - 第一杆组围绕一个或多个水通道，其一般居中设置在燃料束的通道中，并且第二杆组围绕通道的内周壁分布。
-
公开(公告)号：US08548113B2
公开(公告)日：2013-10-01
申请号：US12549823
申请日：2009-08-28
CPC分类号： G21C3/3206 , G21C3/3315 , Y02E30/40
摘要： Example embodiments are directed to upper tie plates for debris mitigation and fuel bundles that use the upper tie plates. Example embodiment tie plates may include a plurality of debris capture elements that overlap each other so as to create debris traps for particulate debris that would fall onto the fuel bundle. Example embodiment fuel bundles may use the upper tie plates for debris mitigation.
摘要翻译： 示例性实施例涉及用于碎片减轻的上连接板和使用上连接板的燃料束。 示例性实施例的连接板可以包括彼此重叠的多个碎片捕获元件，以便产生将落入燃料束上的颗粒碎片的碎屑捕集器。 示例性实施例燃料束可以使用上连接板用于碎片减轻。
-
-
-
-
-
-
-
-
-
搜索结果
121 条记录 (耗时 0.034 秒)
