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1. 发明申请

US20130044850A1 NUCLEAR REACTOR REFUELING METHODS AND APPARATUSES 审中-公开
标题翻译：核反应堆补救方法和装置
公开(公告)号：US20130044850A1
公开(公告)日：2013-02-21
申请号：US13213389
申请日：2011-08-19
申请人： Lewis A. Walton , Mathew W. Ales
发明人： Lewis A. Walton , Mathew W. Ales
IPC分类号： G21C19/10
CPC分类号： G21C19/10 , G21C19/205
摘要： Refueling of a nuclear reactor (40) includes removing a fuel assembly (10). The removal method includes lowering a lifting tool (80) of a crane (44) onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements (82) that surround and vertically overlap a portion (74) of a control rod assembly (70) extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features (26) at the top of the fuel assembly to connect the lifting tool with the fuel assembly. The connected fuel assembly is moved into a spent fuel pool (42) using the crane, and the lifting tool is disconnected from the top of the fuel assembly by unlocking the downwardly extending elements from the corresponding mating features at the top of the fuel assembly.
摘要翻译：核反应堆（40）的加油包括移除燃料组件（10）。拆卸方法包括将起重机（44）的提升工具（80）降低到燃料组件的顶部上。所述降低的提升工具包括多个向下延伸的元件（82），所述多个向下延伸的元件围绕并垂直地重叠在燃料组件的顶部上方延伸的控制杆组件（70）的部分（74）。向下延伸的元件在燃料组件的顶部与对应的配合特征（26）锁定，以将提升工具与燃料组件相连接。使用起重机将连接的燃料组件移动到乏燃料池（42）中，并且通过从燃料组件的顶部处的对应配合特征解锁向下延伸的元件，提升工具从燃料组件的顶部断开。

2. 发明授权

US08526563B2 Terminal elements for coupling connecting rods and control rods in control rod assemblies for a nuclear reactor 有权
标题翻译：在核反应堆的控制杆组件中连接杆和控制杆的端子元件
公开(公告)号：US08526563B2
公开(公告)日：2013-09-03
申请号：US12862124
申请日：2010-08-24
申请人： Scott J. Shargots , Mathew W. Ales
发明人： Scott J. Shargots , Mathew W. Ales
IPC分类号： G21C7/06
CPC分类号： G21C7/117 , G21C7/12 , G21C9/02 , Y02E30/39
摘要： A nuclear reactor includes a pressure vessel, and a control rod assembly (CRA) including at least one movable control rod, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a connecting rod engaged with the CRDM and a terminal element connected with a lower end of the connecting rod and further connected with the at least one control rod. In some embodiments the terminal element includes a first portion comprising a first material having a first density and a second portion comprising a second material having a second density that is greater than the first density. In some embodiments the terminal element has a largest dimension parallel with the connecting rod that is greater than or equal to a largest dimension transverse to the connecting rod.
摘要翻译：核反应堆包括压力容器和控制杆组件（CRA），控制杆组件（CRA）包括至少一个可移动控制杆，用于控制至少一个控制杆的运动的控制杆驱动机构（CRDM）至少一个控制杆和CRDM。联接器包括与CRDM接合的连杆和与连杆的下端连接并与至少一个控制杆连接的端子元件。在一些实施例中，端子元件包括第一部分，其包括具有第一密度的第一材料，第二部分包括具有大于第一密度的第二密度的第二材料。在一些实施例中，端子元件具有与连杆平行的最大尺寸，该尺寸大于或等于横向于连接杆的最大尺寸。

3. 发明申请

US20120099691A1 SUPPORT STRUCTURE FOR A CONTROL ROD ASSEMBLY OF A NUCLEAR REACTOR 有权
标题翻译：核反应堆控制组件的支撑结构
公开(公告)号：US20120099691A1
公开(公告)日：2012-04-26
申请号：US12909252
申请日：2010-10-21
申请人： Scott J. Shargots , Mathew W. Ales
发明人： Scott J. Shargots , Mathew W. Ales
IPC分类号： G21C7/08 , G21C7/117
CPC分类号： G21C7/08 , G21C7/117 , G21C7/12 , G21C21/18 , G21Y2002/104 , Y02E30/39
摘要： A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.
摘要翻译：控制杆引导框架包括限定中心通道的两个或更多个柱状元件的自支撑叠层。柱状元件可以包括在堆叠的相邻柱状元件之间的邻接处配合的配合特征。控制杆引导框架适用于与至少一个控制杆操作连接的控制杆驱动机构（CRDM）和核反应堆堆芯，其中，CRDM将至少一个控制杆移入和移出核反应堆核心在控制杆引导架的引导下。在另一个实施例中，控制杆引导框架包括两个或更多个柱状元件的堆叠，所述柱状元件限定具有作为沿着中心通道的位置的函数的恒定横截面的中心通道。在另一个实施例中，控制杆引导框架包括提供连续控制杆引导的挤压柱状元件。

4. 发明申请

US20100316181A1 INTEGRAL HELICAL COIL PRESSURIZED WATER NUCLEAR REACTOR 有权
标题翻译：综合螺旋线圈加压水核反应堆
公开(公告)号：US20100316181A1
公开(公告)日：2010-12-16
申请号：US12796626
申请日：2010-06-08
申请人： Ted L. Thome , Mathew W. Ales , Billy E. Bingham , John D. Malloy
发明人： Ted L. Thome , Mathew W. Ales , Billy E. Bingham , John D. Malloy
IPC分类号： G21C15/00 , G21C15/25 , F22B27/08
CPC分类号： G21C1/322 , F22B1/023 , F22B21/26 , Y02E30/40 , Y10S376/909
摘要： An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure.
摘要翻译：用于利用螺旋线圈蒸汽发生器，多个内部循环泵以及内部控制杆驱动机构结构生产蒸汽的整体式加压水核反应堆。

5. 发明授权

US09378853B2 Support structure for a control rod assembly of a nuclear reactor 有权
标题翻译：用于核反应堆的控制棒组件的支撑结构
公开(公告)号：US09378853B2
公开(公告)日：2016-06-28
申请号：US12909252
申请日：2010-10-21
申请人： Scott J. Shargots , Mathew W. Ales
发明人： Scott J. Shargots , Mathew W. Ales
IPC分类号： G21C7/12 , G21C7/117
CPC分类号： G21C7/08 , G21C7/117 , G21C7/12 , G21C21/18 , G21Y2002/104 , Y02E30/39
摘要： A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.
摘要翻译：控制杆引导框架包括限定中心通道的两个或更多个柱状元件的自支撑叠层。柱状元件可以包括在堆叠的相邻柱状元件之间的邻接处配合的配合特征。控制杆引导框架适用于与至少一个控制杆操作连接的控制杆驱动机构（CRDM）和核反应堆堆芯，其中，CRDM将至少一个控制杆移入和移出核反应堆核心在控制杆引导架的引导下。在另一个实施例中，控制杆引导框架包括两个或更多个柱状元件的堆叠，所述柱状元件限定具有作为沿着中心通道的位置的函数的恒定横截面的中心通道。在另一个实施例中，控制杆引导框架包括提供连续控制杆引导的挤压柱状元件。

6. 发明授权

US09336910B2 Control rod/control rod drive mechanism couplings 有权
标题翻译：控制杆/控制杆驱动机构联轴器
公开(公告)号：US09336910B2
公开(公告)日：2016-05-10
申请号：US12899739
申请日：2010-10-07
申请人： Scott J. Shargots , Paul K. DeSantis , John P. McLaughlin , Mathew W. Ales
发明人： Scott J. Shargots , Paul K. DeSantis , John P. McLaughlin , Mathew W. Ales
IPC分类号： G21C7/06 , G21C7/10 , G21C7/12 , G21C7/117
CPC分类号： G21C7/14 , G21C7/10 , G21C7/117 , G21C7/12 , G21C7/20 , G21Y2002/30 , G21Y2002/302 , G21Y2004/30 , Y02E30/39
摘要： A nuclear reactor includes a pressure vessel, and a control rod assembly including at least one movable control rod comprising a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a first portion comprising a first material having a first density at room temperature, and a second portion comprising a second material having a second density at room temperature that is greater than the first density. In some embodiments the coupling includes a connecting rod including a hollow or partially hollow connecting rod tube comprising a first material having a first density and a filler disposed in the hollow or partially hollow connecting rod tube, the filler comprising a second material having a second density greater than the first density.
摘要翻译：核反应堆包括压力容器和包括至少一个包括中子吸收材料的可移动控制棒的控制杆组件，用于控制至少一个控制棒的运动的控制棒驱动机构（CRDM）和可操作地连接所述至少一个控制杆和所述CRDM。联接器包括第一部分，其包括在室温下具有第一密度的第一材料，第二部分包括在室温下具有大于第一密度的第二密度的第二材料。在一些实施例中，联接器包括连杆，该连杆包括中空或部分中空的连杆管，其包括具有第一密度的第一材料和设置在中空或部分中空的连杆管中的填料，填料包括具有第二密度的第二材料大于第一密度。

7. 发明授权

US09177674B2 Compact nuclear reactor 有权
标题翻译：紧凑型核反应堆
公开(公告)号：US09177674B2
公开(公告)日：2015-11-03
申请号：US12911572
申请日：2010-10-25
申请人： John D. Malloy , Mathew W. Ales
发明人： John D. Malloy , Mathew W. Ales
IPC分类号： G21C7/06 , G21C1/08 , G21C1/32 , G21C7/08
CPC分类号： G21C1/322 , G21C1/086 , G21C7/08 , G21C15/243 , Y02E30/32 , Y02E30/39
摘要： A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG.
摘要翻译：加压水核反应堆（PWR）包括设置在大致圆柱形的压力容器中的一次性蒸汽发生器（OTSG）和与中央提升管的开口端间隔开的分隔板。压力容器和分隔板的密封部分限定了由分隔板与压力容器的剩余内部容积隔开的整体加压器体积。内部控制杆驱动机构（CRDM）具有至少包括设置在压力容器内部的电动机和导螺杆的所有机械和电动汽车部件。可选地，CRDM单元在两个或更多个不同级别交错，使得没有两个相邻的CRDM单元处于相同的水平。内部主冷却剂泵具有所有机械和电动汽车部件，其包括至少一个电动机和至少一个设置在压力容器内的叶轮。可选地，泵和/或CRDM布置在OTSG的下方。

8. 发明申请

US20150206605A1 CONTROL ROD/CONTROL ROD DRIVE MECHANISM COUPLINGS 有权
标题翻译：控制杆/控制杆驱动机构联轴器
公开(公告)号：US20150206605A1
公开(公告)日：2015-07-23
申请号：US12899739
申请日：2010-10-07
申请人： Scott J. Shargots , Paul K. DeSantis , John P. McLaughlin , Mathew W. Ales
发明人： Scott J. Shargots , Paul K. DeSantis , John P. McLaughlin , Mathew W. Ales
IPC分类号： G21C7/14 , G21C7/117
CPC分类号： G21C7/14 , G21C7/10 , G21C7/117 , G21C7/12 , G21C7/20 , G21Y2002/30 , G21Y2002/302 , G21Y2004/30 , Y02E30/39
摘要： A nuclear reactor includes a pressure vessel, and a control rod assembly including at least one movable control rod comprising a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a first portion comprising a first material having a first density at room temperature, and a second portion comprising a second material having a second density at room temperature that is greater than the first density. In some embodiments the coupling includes a connecting rod including a hollow or partially hollow connecting rod tube comprising a first material having a first density and a filler disposed in the hollow or partially hollow connecting rod tube, the filler comprising a second material having a second density greater than the first density.
摘要翻译：核反应堆包括压力容器和包括至少一个包括中子吸收材料的可移动控制棒的控制杆组件，用于控制至少一个控制棒的运动的控制棒驱动机构（CRDM）和可操作地连接所述至少一个控制杆和所述CRDM。联接器包括第一部分，其包括在室温下具有第一密度的第一材料，第二部分包括在室温下具有大于第一密度的第二密度的第二材料。在一些实施例中，联接器包括连杆，该连杆包括中空或部分中空的连杆管，其包括具有第一密度的第一材料和设置在中空或部分中空的连杆管中的填料，填料包括具有第二密度的第二材料大于第一密度。

9. 发明授权

US08971477B2 Integral helical coil pressurized water nuclear reactor 有权
标题翻译：积分螺旋线圈加压水核反应堆
公开(公告)号：US08971477B2
公开(公告)日：2015-03-03
申请号：US12796626
申请日：2010-06-08
申请人： Ted L. Thome , Mathew W. Ales , Billy E. Bingham , John D. Malloy
发明人： Ted L. Thome , Mathew W. Ales , Billy E. Bingham , John D. Malloy
IPC分类号： G21C1/00 , G21C1/32 , F22B1/02 , F22B21/26
CPC分类号： G21C1/322 , F22B1/023 , F22B21/26 , Y02E30/40 , Y10S376/909
摘要： An integral pressurized water nuclear reactor for the production of steam utilizing a helical coil steam generator, a plurality of internal circulation pumps, and an internal control rod drive mechanism structure.
摘要翻译：用于利用螺旋线圈蒸汽发生器，多个内部循环泵以及内部控制杆驱动机构结构生产蒸汽的整体式加压水核反应堆。

10. 外观设计

USD691084S1 Reactor vessel 有权
标题翻译：反应釜
公开(公告)号：USD691084S1
公开(公告)日：2013-10-08
申请号：US29389704
申请日：2011-04-15
申请人： Mathew W. Ales
设计人： Mathew W. Ales

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