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1. 发明授权

US10446284B2 Instrumentation conduit housing 有权
公开(公告)号：US10446284B2
公开(公告)日：2019-10-15
申请号：US15377601
申请日：2016-12-13
申请人： TerraPower, LLC
发明人： Peter W. Gibbons , P. Harley Park
IPC分类号： G21C17/116 , G21C1/02 , G21C15/02 , G21C5/00
摘要： A conduit housing includes a top face, a pair of side faces disposed opposite each other and adjacent to the top face, a front side, and a rear side. The top face includes a plurality of vertical conduit ports arranged in a plurality of rows. The front side is positioned between the pair of side faces and defines a plurality of stepped faces. The rear side is disposed opposite the front side and adjacent the top face. The stepped faces include a plurality of downward faces and each of the plurality of downward faces defines a downward face plane. The stepped faces also include a plurality of upward faces, where each of the plurality of upward faces defines an upward face plane. Each upward face includes a plurality of pitched conduit ports.

2. 发明授权

US09502145B2 Nuclear reactor operation and simulation 有权
标题翻译：核反应堆运行和模拟
公开(公告)号：US09502145B2
公开(公告)日：2016-11-22
申请号：US12565402
申请日：2009-09-23
申请人： Jon D. McWhirter , Charles Whitmer , Lowell L. Wood, Jr. , George B. Zimmerman
发明人： Jon D. McWhirter , Charles Whitmer , Lowell L. Wood, Jr. , George B. Zimmerman
IPC分类号： G21C17/00 , G21D3/00 , G21C1/02 , G21C5/00 , G21C7/00
CPC分类号： G21D3/001 , G06F17/5009 , G21C1/026 , G21C5/00 , G21C7/00 , G21C17/00 , G21D2003/002 , Y02E30/34 , Y02E30/39
摘要： Illustrative embodiments provide for the operation and simulation of the operation of fission reactors. Illustrative embodiments and aspects include, without limitation, nuclear fission reactors and reactor modules, including modular nuclear fission reactors and reactor modules, nuclear fission deflagration wave reactors and reactor modules, modular nuclear fission deflagration wave reactors and modules, methods of operating nuclear reactors and modules including the aforementioned, methods of simulating operating nuclear reactors and modules including the aforementioned, and the like.
摘要翻译：示例性实施例提供了对裂变反应堆的操作的操作和模拟。说明性的实施方案和方面包括但不限于核裂变反应堆和反应堆模块，包括模块式核裂变反应堆和反应堆模块，核裂变爆燃波反应堆和反应堆模块，模块式核裂变爆燃波反应堆和模块，运行核反应堆和模块的方法包括前述的模拟运行的核反应堆的方法和包括上述的模块等。

3. 发明授权

US09093183B2 Heavy radial neutron reflector for pressurized water reactors 有权
标题翻译：用于压水反应堆的重径向中子反射器
公开(公告)号：US09093183B2
公开(公告)日：2015-07-28
申请号：US13721138
申请日：2012-12-20
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： Alexander W. Harkness
IPC分类号： G21C11/06 , G21C5/00
CPC分类号： G21C11/06 , Y02E30/40
摘要： A heavy radial neutron reflector for a pressurized water reactor that employs elongated lengths of round bar stock closely packed in either a triangular or rectangular array extending between former plates of a core shroud between the core barrel and the baffle plates which outline the periphery of the reactor core and are formed in axial and circumferential modules. Flow channels are formed in the long gaps between the adjacent round bar stock that communicates cooling water that enters through the core barrel at the top of the shroud and flows down through openings in the former plates to the bottom of the neutron reflector where it exits through a lower baffle orifice to join other cooling water flowing up through the lower core support plate.
摘要翻译：用于加压水反应器的重径向中子反射器，其采用细长的圆棒坯料，其密封地填充在三角形或矩形阵列之间，该三角形或矩形阵列在核心筒和挡板之间的芯板护罩的前板之间延伸，其围绕反应器的周边并且形成在轴向和周向模块中。流动通道形成在相邻的圆棒坯料之间的长间隙中，其连通通过在护罩顶部的芯筒进入的冷却水，并且通过前板中的开口向下流过中子反射器的底部，在其中它通过下部挡板孔，以连接通过下芯支撑板向上流动的其它冷却水。

4. 发明授权

US08681924B2 Single-plate neutron absorbing apparatus and method of manufacturing the same 有权
标题翻译：单板中子吸收装置及其制造方法
公开(公告)号：US08681924B2
公开(公告)日：2014-03-25
申请号：US12645846
申请日：2009-12-23
申请人： Evan Rosenbaum , Thomas G. Haynes, III , Krishna P. Singh
发明人： Evan Rosenbaum , Thomas G. Haynes, III , Krishna P. Singh
IPC分类号： G21K1/00 , G21F1/08 , G21C5/12 , G21F1/00 , G21C5/00
CPC分类号： G21C19/07 , G21F1/08
摘要： A neutron absorbing insert for use in a fuel rack and method of manufacturing the same. In ones aspect, the invention is a neutron absorbing apparatus comprising: a plate structure having a first wall and a second wall that is non-coplanar to the first wall; the first and second walls being formed by a single panel of a metal matrix composite having neutron absorbing particulate reinforcement that is bent into the non-coplanar arrangement along a crease; and a plurality of spaced-apart holes formed into the single panel along the crease prior to bending.
摘要翻译：一种用于燃料支架的中子吸收插入件及其制造方法。在一方面，本发明是一种中子吸收装置，包括：板结构，其具有与第一壁非共面的第一壁和第二壁; 所述第一和第二壁由具有中子吸收颗粒增强物的金属基复合材料的单块形成，所述中子吸收颗粒增强材料沿着折痕弯曲成非共面布置; 以及在弯曲之前沿着折痕形成为单个面板的多个间隔开的孔。

5. 发明申请

US20140064431A1 NOZZLE REPAIRING METHOD AND NUCLEAR REACTOR VESSEL 有权
标题翻译：喷嘴修复方法和核反应堆船
公开(公告)号：US20140064431A1
公开(公告)日：2014-03-06
申请号：US13853610
申请日：2013-03-29
申请人： MITSUBISHI HEAVY INDUSTRIES, LTD.
发明人： Takeshi Yamamoto , Tomochika Hamamoto , Nobuyuki Hori , Tsuyoshi Nishimura , Hideshi Sakashita
IPC分类号： B23P6/04 , G21C5/00
CPC分类号： B23P6/04 , G21C5/00 , G21C13/02 , G21C13/036 , G21C17/017 , G21C19/207 , Y02E30/40 , Y10T29/49734 , Y10T29/49737
摘要： It is possible to improve the workability and the stress corrosion resistance by easily performing a repairing operation in a nozzle repairing method and a nuclear reactor vessel. The repairing method includes: removing a first connection portion ((trepanned portion) 208) with respect to an in-core instrument tube (204) in a groove-welding portion (206); removing the in-core instrument tube (204) from a lower mirror (66); leaving and grooving a second connection portion ((existing welding portion) 211) with respect to the lower mirror (66) in the groove-welding portion (206); inserting a new in-core instrument tube (204A) into an attachment hole (203); and groove-welding (so as to form a new groove-welding portion (213)) the inner side of the lower mirror (66) so as to fix the new in-core instrument tube (204A).
摘要翻译：通过在喷嘴修复方法和核反应堆容器中容易进行修理操作，可以提高加工性和耐应力腐蚀性。所述修复方法包括：相对于槽焊接部分（206）中的核心内仪表管（204）去除第一连接部分（（棘手部分）208）; 从下反射镜（66）移除核心内仪器管（204）; 在凹槽焊接部分（206）中相对于下反射镜（66）留下并切割第二连接部分（（存在的焊接部分）211）; 将新的核心仪器管（204A）插入连接孔（203）中; 以及下反射镜（66）的内侧的沟槽焊接（以形成新的槽焊接部分（213）），以固定新的核心仪表管（204A）。

6. 发明授权

US08532245B2 Core shroud corner joints 有权
标题翻译：核心护角角接头
公开(公告)号：US08532245B2
公开(公告)日：2013-09-10
申请号：US12634836
申请日：2009-12-10
申请人： Charles B. Gilmore , David R. Forsyth
发明人： Charles B. Gilmore , David R. Forsyth
IPC分类号： G21C5/08 , G21C15/02 , G21C5/00 , G21C15/00
CPC分类号： G21C21/00 , G21C3/322 , G21C5/08 , G21C13/02 , Y02E30/38
摘要： A core shroud is provided, which includes a number of planar members, a number of unitary corners, and a number of subassemblies each comprising a combination of the planar members and the unitary corners. Each unitary corner comprises a unitary extrusion including a first planar portion and a second planar portion disposed perpendicularly with respect to the first planar portion. At least one of the subassemblies comprises a plurality of the unitary corners disposed side-by-side in an alternating opposing relationship. A plurality of the subassemblies can be combined to form a quarter perimeter segment of the core shroud. Four quarter perimeter segments join together to form the core shroud.
摘要翻译：提供了一种芯护罩，其包括多个平面构件，多个单一角部以及各自包括平面构件和单个角部的组合的多个子组件。每个单一角落包括一个单一的挤压件，包括第一平面部分和相对于第一平面部分垂直设置的第二平面部分。子组件中的至少一个包括以交替相对的关系并排布置的多个整体角。多个子组件可以组合以形成芯套管的四分之一周边段。四个四分之一周边段连接在一起形成核心护罩。

7. 发明授权

US07873138B2 Structure and method for bolting neutron reflector 有权
标题翻译：螺栓中子反射器的结构和方法
公开(公告)号：US07873138B2
公开(公告)日：2011-01-18
申请号：US10311602
申请日：2002-04-25
申请人： Makoto Nakajima , Hirokazu Shoumura , Kenji Umeda
发明人： Makoto Nakajima , Hirokazu Shoumura , Kenji Umeda
IPC分类号： G21C5/00
CPC分类号： G21C11/06 , G21Y2002/206 , G21Y2002/303 , G21Y2004/301 , Y02E30/40
摘要： A neutron reflector bolt fastening structure is disclosed in which even upon relaxation in the fastening forces thereof being generated in tie rods for divided stage portions as a result of neutron irradiation, it is possible to press the neutron reflector firmly against a core vessel. The neutron reflector bolt fastening structure includes: a neutron reflector which includes of a plurality of divided stage portions and situated in a core vessel in a reactor vessel; a plurality of tie rods for fixing the neutron reflector to the core vessel; and a plurality of bolts for exclusively fixing the lowermost stage portion of the plurality of stage portions of the neutron reflector to the core vessel.
摘要翻译：公开了一种中子反射器螺栓紧固结构，其中即使在由于中子照射而产生在用于分割台部分的拉杆中的紧固力的松弛中，也可以将中子反射器牢固地压靠在核心容器上。中子反射器螺栓紧固结构包括：中子反射器，其包括多个分级台部并且位于反应器容器中的核心容器中; 多个用于将中子反射器固定到核心容器的拉杆; 以及用于将中子反射器的多个台阶部分的最下段部分专门固定到核心容器的多个螺栓。

8. 发明申请

US20050015227A1 Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors 有权
标题翻译：用于生成核反应堆燃料束设计数据库的方法，安排和计算机程序
公开(公告)号：US20050015227A1
公开(公告)日：2005-01-20
申请号：US10879122
申请日：2004-06-30
申请人： David Kropaczek , Mehdi Asgari , Christian Oyarzun , Steven Sutton , William Russell , William Cline
发明人： David Kropaczek , Mehdi Asgari , Christian Oyarzun , Steven Sutton , William Russell , William Cline
IPC分类号： G21C17/00 , G06F17/10 , G06F17/50 , G06G7/54 , G06G7/62 , G21C1/00 , G21C3/32 , G21C5/00 , G21C19/20 , G21C23/00
CPC分类号： G21D3/001 , G21C3/00 , G21C19/205 , G21D2003/002 , G21Y2002/30 , G21Y2004/401 , Y02E30/40
摘要： A method, arrangement and computer program is described for generating a database of selectable fresh fuel bundle designs usable in one or more nuclear reactors. In an example, an initial population of candidate fresh fuel bundle designs may be generated and a set of rod-type changes to make to a given candidate in the initial population may be established. A given candidate fresh fuel bundle may be modified by making at least one rod-type change from the set therein. A core loaded with the modified bundle design may be simulated to generate bundle performance outputs. The bundle performance outputs may be ranked based on a plurality of user-input limits. The modified candidate fresh fuel bundle design may be stored, if the bundle performance outputs meet, or are within an accepted margin to, the user-input limits, so as to generate the database.
摘要翻译：描述了用于生成可用于一个或多个核反应堆中的可选择的新鲜燃料束设计的数据库的方法，布置和计算机程序。在一个示例中，可以生成候选新鲜燃料束设计的初始种群，并且可以建立对初始种群中的给定候选物进行的一组条形变化。给定的候选新鲜燃料束可以通过从其中的组中进行至少一个棒式改变来改变。可以模拟加载修改的捆绑设计的核心，以生成捆绑包性能输出。可以基于多个用户输入限制对捆绑性能输出进行排名。如果捆绑性能输出满足或在用户输入限制内的可接受余量内，则可以存储修改后的候选新鲜燃料束设计，以便生成数据库。

9. 发明授权

US5583899A Removable retrofit shroud for a boiling water nuclear reactor and associated method 失效
标题翻译：沸水核反应堆可拆卸改装护罩及相关方法
公开(公告)号：US5583899A
公开(公告)日：1996-12-10
申请号：US373377
申请日：1995-01-17
申请人： Charles W. Relf
发明人： Charles W. Relf
IPC分类号： G21C5/00 , G21C1/08 , G21C5/10 , G21C13/00 , G21C15/02 , G21C19/02 , G21C15/00
CPC分类号： G21C5/10 , G21C1/084 , G21Y2002/104 , G21Y2004/50 , Y02E30/31
摘要： In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the shroud spaced radially inwardly of a side wall of the pressure vessel, and an annular pump deck welded in a place in an annular radial space between the core shroud and the side wall of the pressure vessel. The shroud provided with a radially outwardly extending flange seated on and removably secured to the pump deck. Wedge elements are interposed between flange portions and the side wall.
摘要翻译：在核反应堆的压力容器中，该核反应堆包含封闭在核心护罩内的芯组件，护罩与压力容器的侧壁径向向内隔开，以及环形泵座，其焊接在芯套之间的环形径向空间和压力容器的侧壁。护罩设有一个径向向外延伸的凸缘，该法兰可以安装在可拆卸地固定在泵甲板上。楔形元件插在凸缘部分和侧壁之间。

10. 发明授权

US5446773A Fast Reactor Core 失效
标题翻译：快速反应堆核心
公开(公告)号：US5446773A
公开(公告)日：1995-08-29
申请号：US341972
申请日：1994-11-16
申请人： Toshio Wakabayashi
发明人： Toshio Wakabayashi
IPC分类号： G21C5/00 , G21C3/28 , G21C3/328 , G21C3/62 , G21C5/02 , G21D9/00 , G21F9/00 , G21G1/02
CPC分类号： G21C3/28 , G21C3/328 , G21C5/02 , G21D9/00 , Y02E30/34 , Y02E30/38 , Y10S376/901
摘要： The invention provides a heterogeneously loaded type of fast reactor core in which a reduced number of target fuel assemblies containing minor actinide nuclides are heterogeneously dispersed and loaded. A wrapper tube for each of the target fuel assemblies is of the same shape and size as a hexagonal wrapper tube for an ordinary core fuel assembly. Each of target fuel rods within the wrapper tube contains 20 to 50% of minor actinide nuclides, and has a diameter more reduced than that of an ordinary core fuel rod. The number of the ordinary core fuel rods loaded in the ordinary core fuel assembly is 271 while the number of the target fuel rods loaded in the target fuel assembly is 331 or 397. Thirty to 50 such target fuel assemblies are heterogeneously dispersed and loaded in the fast reactor core.
摘要翻译：本发明提供了一种异质负载型快堆，其中减少数量的含少量锕系元素的目标燃料组件是非均匀分散和加载的。用于每个目标燃料组件的包装管具有与用于普通核燃料组件的六边形包装管相同的形状和尺寸。包装管内的每个目标燃料棒包含20-50％的次要锕系核素，其直径比普通核心燃料棒的直径更小。装在普通核燃料组件中的普通核心燃料棒的数量是271，而装载在目标燃料组件中的目标燃料棒的数量是331或397。这样的目标燃料组件的三十到五十个这样的目标燃料组件被非均匀地分散并装载在快堆芯。

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