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1. 发明申请

US20140198889A1 METHOD AND APPARATUS FOR THE SHIELDED RELOCATION OF A NUCLEAR COMPONENT 有权
标题翻译：核成分的屏蔽转移的方法和装置
公开(公告)号：US20140198889A1
公开(公告)日：2014-07-17
申请号：US13741664
申请日：2013-01-15
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： Alexander W. Harkness
IPC分类号： G21C19/105
CPC分类号： G21C19/105 , G21C19/16 , G21C19/205 , G21C19/32 , G21F5/008 , G21F5/14
摘要： A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement.
摘要翻译：一种核部件传输装置，其将屏蔽的罐结合到常规核加油机的桅杆设计中。固定式桅杆内的可移动桅杆望远镜，其连接到用于横向定位的桥。罐允许添加屏蔽，其随着可移动桅杆的移动而定位，而不需要附加的电动部件来在核部件运动期间展开屏蔽。当可移动的桅杆提升核部件时，核部件被拉入屏蔽罐。然后将核部件放入也装有屏蔽罐的转运车中。在不暴露核组件导致完全屏蔽运动的情况下进行转移。

2. 发明授权

US09478320B2 Method for in-core instrumentation withdrawal from the core of a pressurized water reactor 有权
标题翻译：核心仪表从压水反应堆核心退出的方法
公开(公告)号：US09478320B2
公开(公告)日：2016-10-25
申请号：US14461555
申请日：2014-08-18
申请人： Westinghouse Electric Company LLC
发明人： Radu O. Pomirleanu , Alexander W. Harkness
IPC分类号： G21C19/19 , G21C13/02 , G21C19/20 , G21C1/32
CPC分类号： G21C19/19 , G21C1/322 , G21C5/10 , G21C13/02 , G21C17/116 , G21C19/205 , Y02E30/40
摘要： A method of removing the upper internals assembly from a nuclear reactor pressure vessel for refueling that simultaneously disconnects two or more of the in-core instrument thimble assemblies from the reactor vessel penetrations through which their signal cables extend. The signal cables are connected to the penetrations with an electrical connector that supports the two or more in-core instrumentation thimble assembly signal leads. Before the electrical connector is disconnected, water in the vessel is lowered below the connection so that the process is performed in a dry environment.
摘要翻译：从用于加油的核反应堆压力容器移除上部内件组件的方法，其同时将两个或更多个核心内仪器套管组件与其信号电缆延伸穿过的反应堆容器穿透断开。信号电缆通过支撑两个或多个核心仪表套管组件信号引线的电连接器连接到穿孔。在电连接器断开之前，容器中的水被降低到连接下方，使得该过程在干燥的环境中进行。

3. 发明申请

US20160118150A1 Method and Apparatus for the Shielded Relocation of a Nuclear Component 有权
标题翻译：核组件屏蔽重新定位的方法和装置
公开(公告)号：US20160118150A1
公开(公告)日：2016-04-28
申请号：US14936893
申请日：2015-11-10
申请人： Westinghouse Electric Company LLC
发明人： Alexander W. Harkness
IPC分类号： G21C19/105 , G21C19/32
CPC分类号： G21C19/105 , G21C19/16 , G21C19/205 , G21C19/32 , G21F5/008 , G21F5/14
摘要： A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement.
摘要翻译：一种核部件传输装置，其将屏蔽的罐结合到常规核加油机的桅杆设计中。固定式桅杆内的可移动桅杆望远镜，其连接到用于横向定位的桥。罐允许添加屏蔽，其随着可移动桅杆的移动而定位，而不需要附加的电动部件来在核部件运动期间展开屏蔽。当可移动的桅杆提升核部件时，核部件被拉入屏蔽罐。然后将核部件放入也装有屏蔽罐的转运车中。在不暴露核组件导致完全屏蔽运动的情况下进行转移。

4. 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。

5. 发明授权

US09406408B2 Passive system for cooling the core of a nuclear reactor 有权
公开(公告)号：US09406408B2
公开(公告)日：2016-08-02
申请号：US14918665
申请日：2015-10-21
申请人： Westinghouse Electric Company LLC
发明人： Alexander W. Harkness
IPC分类号： G21C15/18
CPC分类号： G21C15/18 , G21C19/07 , G21D3/06 , Y02E30/32
摘要： A system for passively cooling nuclear fuel in a pressurized water reactor during refueling that employs gravity and alignment of valves using battery reserves or fail in a safe position configurations to maintain the water above the reactor core during reactor disassembly and refueling. A large reserve of water is maintained above the elevation of and in fluid communication with the spent fuel pool and is used to remove decay heat from the reactor core after the reaction within the core has been successfully stopped. Decay heat is removed by boiling this large reserve of water, which will enable the plant to maintain a safe shutdown condition without outside support for many days.

6. 发明申请

US20160118147A1 Passive System for Cooling the Core of a Nuclear Reactor 有权
标题翻译：用于冷却核反应堆核心的被动系统
公开(公告)号：US20160118147A1
公开(公告)日：2016-04-28
申请号：US14918665
申请日：2015-10-21
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： Alexander W. Harkness
IPC分类号： G21C15/18
CPC分类号： G21C15/18 , G21C19/07 , G21D3/06 , Y02E30/32
摘要： A system for passively cooling nuclear fuel in a pressurized water reactor during refueling that employs gravity and alignment of valves using battery reserves or fail in a safe position configurations to maintain the water above the reactor core during reactor disassembly and refueling. A large reserve of water is maintained above the elevation of and in fluid communication with the spent fuel pool and is used to remove decay heat from the reactor core after the reaction within the core has been successfully stopped. Decay heat is removed by boiling this large reserve of water, which will enable the plant to maintain a safe shutdown condition without outside support for many days.
摘要翻译：一种用于在加油期间在加压水反应堆中被动地冷却核燃料的系统，其使用蓄电池储备的重力和对准阀或在安全位置构型中失效，以在反应堆拆卸和加油期间将水保持在反应堆堆芯上方。大量储备的水被保持在废燃料池的高度和流体连通之外，并且在核心中的反应已经成功地停止之后被用于去除反应堆堆芯的腐蚀热。通过煮沸大量储备的水来消除朽烂的热量，这将使得工厂能够在没有外部支持的情况下保持安全关闭条件多天。

7. 发明授权

US09275765B2 Method and apparatus for the shielded relocation of a nuclear component 有权
标题翻译：核组件屏蔽重定位的方法和装置
公开(公告)号：US09275765B2
公开(公告)日：2016-03-01
申请号：US13741664
申请日：2013-01-15
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： Alexander W. Harkness
IPC分类号： G21C19/105 , G21F5/008 , G21C19/16
CPC分类号： G21C19/105 , G21C19/16 , G21C19/205 , G21C19/32 , G21F5/008 , G21F5/14
摘要： A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement.
摘要翻译：一种核部件传输装置，其将屏蔽的罐结合到常规核加油机的桅杆设计中。固定式桅杆内的可移动桅杆望远镜，其连接到用于横向定位的桥。罐允许添加屏蔽，其随着可移动桅杆的移动而定位，而不需要额外的机动部件来在核部件运动期间展开屏蔽。当可移动的桅杆提升核部件时，核部件被拉入屏蔽罐。然后将核部件放入也装有屏蔽罐的转运车中。在不暴露核组件导致完全屏蔽运动的情况下进行转移。

8. 发明申请

US20160049212A1 Method for In-Core Instrumentation Withdrawal From the Core of a Pressurized Water Reactor 有权
标题翻译：核心设备从加压水反应堆核心提取的方法
公开(公告)号：US20160049212A1
公开(公告)日：2016-02-18
申请号：US14461555
申请日：2014-08-18
申请人： Westinghouse Electric Company LLC
发明人： Radu O. Pomirleanu , Alexander W. Harkness
IPC分类号： G21C19/19
CPC分类号： G21C19/19 , G21C1/322 , G21C5/10 , G21C13/02 , G21C17/116 , G21C19/205 , Y02E30/40
摘要： A method of removing the upper internals assembly from a nuclear reactor pressure vessel for refueling that simultaneously disconnects two or more of the in-core instrument thimble assemblies from the reactor vessel penetrations through which their signal cables extend. The signal cables are connected to the penetrations with an electrical connector that supports the two or more in-core instrumentation thimble assembly signal leads. Before the electrical connector is disconnected, water in the vessel is lowered below the connection so that the process is performed in a dry environment.
摘要翻译：从用于加油的核反应堆压力容器移除上部内件组件的方法，其同时将两个或更多个核心内仪器套管组件与其信号电缆延伸穿过的反应堆容器穿透断开。信号电缆通过支撑两个或多个核心仪表套管组件信号引线的电连接器连接到穿孔。在电连接器断开之前，容器中的水被降低到连接下方，使得该过程在干燥的环境中进行。

9. 发明授权

US10102935B2 Method of removing upper internals from a nuclear reactor pressurized vessel 有权
公开(公告)号：US10102935B2
公开(公告)日：2018-10-16
申请号：US15066230
申请日：2016-03-10
申请人： Westinghouse Electric Company LLC
发明人： Alexander W. Harkness
IPC分类号： G21C19/20 , G21C19/02 , G21C19/10 , G21C1/08 , G21C1/32
摘要： A lifting fixture for removing the upper internals from a nuclear reactor to provide access to the core during a refueling that does not require flooding of a refueling canal. A shield plate is integral to a lifting rig used to remove the upper internals. The shield plate is sized to be supported on the reactor vessel upper flange and to cover the reactor vessel opening with the closure head removed. The shield plate has openings that are in-line with the control rod assembly drive rod travel housings. Control rod assembly drive rods can be accessed through the openings. The lifting rig allows personnel to decouple the drive rods from the rod cluster control assemblies. The lifting fixture enables the decoupled drive rods to be lifted from the core with the upper internals, while shielding maintenance personnel without flooding the area above the reactor.

10. 发明授权

US09318227B2 Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel 有权
标题翻译：从核反应堆加压容器中去除上部内件的装置和方法
公开(公告)号：US09318227B2
公开(公告)日：2016-04-19
申请号：US13741737
申请日：2013-01-15
申请人： WESTINGHOUSE ELECTRIC COMPANY LLC
发明人： Alexander W. Harkness
IPC分类号： G21C19/10 , G21C19/02 , G21C19/20 , G21C1/32
CPC分类号： G21C19/02 , G21C1/086 , G21C1/32 , G21C19/10 , G21C19/20 , G21C19/207
摘要： A lifting fixture for removing the upper internals from a nuclear reactor to provide access to the core during a refueling that does not require flooding of a refueling canal. A shield plate is integral to a lifting rig used to remove the upper internals. The shield plate is sized to be supported on the reactor vessel upper flange and to cover the reactor vessel opening with the closure head removed. The shield plate has openings that are in-line with the control rod assembly drive rod travel housings. Control rod assembly drive rods can be accessed through the openings. The lifting rig allows personnel to decouple the drive rods from the rod cluster control assemblies. The lifting fixture enables the decoupled drive rods to be lifted from the core with the upper internals while shielding maintenance personnel without use of flooding the area above the reactor.
摘要翻译：一种用于从核反应堆移除上部内部件的提升固定装置，用于在不需要加油渠的淹水的加油中提供对核心的通路。屏蔽板与用于去除上部内部件的起重机组成一体。屏蔽板的尺寸被设计成支撑在反应堆容器上凸缘上并且在去除了封闭头的情况下覆盖反应堆容器开口。屏蔽板具有与控制杆组件驱动杆移动壳体成一直线的开口。控制杆组件驱动杆可通过开口进入。起重机允许人员将驱动杆与杆组控制组件分离。提升固定装置可以使脱钩的驱动杆与上部内部件从芯体提升，同时屏蔽维护人员，而不用淹没反应堆上方的区域。

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