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公开(公告)号：US20140072090A1
公开(公告)日：2014-03-13
申请号：US13613281
申请日：2012-09-13
申请人： John R. BASS , Robert J. GINSBERG
发明人： John R. BASS , Robert J. GINSBERG
IPC分类号： G21C15/00
摘要： A method and system for an alternate energy removal path for a reactor pressure vessel (RPV) of a light water reactor. A pair of manually operated containment isolation valves, one located inside and one located outside of primary containment, are used to open and close a steam extraction line that is fluidly coupled between the RPV and a heat sink. The heat sink is located outside of primary containment. A source of external electrical power is not required to operate the system or perform the method.
摘要翻译： 用于轻水反应堆的反应堆压力容器（RPV）的替代能量去除路径的方法和系统。 一对手动操作的安全壳隔离阀，一个位于内部的一个，一个位于初级容纳物的外部，用于打开和关闭流体耦合在RPV和散热器之间的蒸汽抽出管线。 散热器位于主要安全壳之外。 不需要外部电源来操作系统或执行该方法。
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2.发明申请公开(公告)号：US20130170596A1
公开(公告)日：2013-07-04
申请号：US13340678
申请日：2011-12-30
IPC分类号： G21C17/112
CPC分类号： G01K1/026 , G01K13/00 , G21C17/112
摘要： A temperature sensor array includes several temperature sensors at different positions for installation within an instrumentation tube of a nuclear reactor. The temperature sensors measure temperature at multiple axial positions of the nuclear reactor, and plant operators are able to access and interpret this measurement data. Temperatures associated with vessel coolant boiling or loss and/or fuel damage can be detected by the temperature sensors to permit more direct determinations of core fluid levels. Multiple temperature sensor arrays permit vessel fluid levels and conditions to be measured at multiple core locations.
摘要翻译： 温度传感器阵列包括用于安装在核反应堆的仪表管内的不同位置处的多个温度传感器。 温度传感器测量核反应堆多个轴向位置的温度，工厂操作人员可以访问和解释此测量数据。 通过温度传感器检测与容器冷却剂沸腾或损失和/或燃料损坏相关的温度，以允许更直接地确定核心液体水平。 多个温度传感器阵列允许在多个核心位置测量血管液体水平和状况。
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公开(公告)号：US10395784B2
公开(公告)日：2019-08-27
申请号：US13609926
申请日：2012-09-11
摘要： A method and system for external alternate suppression pool cooling for a Boiling Water Nuclear Reactor (BWR) that does not breach the Mark I primary containment. The external cooling system may include a heat sink fluidly coupled to cooling coils surrounding the suppression pool. Cool water may be pumped through the cooling coils without the need for normal plant electrical power, which is ideal during a plant emergency. The cooling system may also be operated and controlled from a remote location to protect the safety of plant personnel.
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公开(公告)号：US20130170594A1
公开(公告)日：2013-07-04
申请号：US13340675
申请日：2011-12-30
CPC分类号： G21D1/04 , F04D15/0077 , F04D29/106 , F04D29/146 , F16J15/008 , F16J15/164 , G21C15/243 , Y02E30/40
摘要： A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump.
摘要翻译： 泵泄漏减轻装置包括在泵的外表面上的一个或多个夹紧臂，该夹臂可由偏置元件驱动以抵靠泵的轴来密封或减少通过泵的击穿的流体流动。 偏置元件仅在阈值温度下接合，例如当需要额外的密封时与击穿孔故障相关联的那些温度。 任何数量和形状的夹臂可用于实现所需的密封和基于泵的几何形状。 密封剂表面和/或保持机构可用于泄漏缓解装置以增强整个泵故障瞬变情况下的流体阻塞。 泵泄漏减轻装置安装在各种不同泵类型的外部，因此可以被安装，致动，操纵，分离和/或移除，而不必破坏或拆卸泵。
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公开(公告)号：US20160118148A1
公开(公告)日：2016-04-28
申请号：US14883414
申请日：2015-10-14
申请人： Robert A. AYER , Robert J. GINSBERG , John R. BASS
发明人： Robert A. AYER , Robert J. GINSBERG , John R. BASS
CPC分类号： G21C15/182 , G21D1/02 , G21D3/06 , Y02E30/40
摘要： A method of transferring heat from a nuclear plant may include: connecting a heat transfer system to the nuclear plant; and using the heat transfer system to transfer heat from the nuclear plant. The heat transfer system may include: a piping system that includes first and second connectors; a heat exchanger; a pump; and a power source. The heat transfer system may not be connected to the nuclear plant during normal plant power operations. The power source may be independent of a normal electrical power distribution system for the nuclear plant. The power source may be configured to power the pump. The piping system may be configured to connect the heat exchanger and pump. The first and second connectors may be configured to connect the heat transfer system to a fluid system of the nuclear plant.
摘要翻译： 从核电厂转移热量的方法可包括：将热传递系统连接到核电厂; 并使用传热系统从核电站传递热量。 传热系统可以包括：管道系统，其包括第一和第二连接器; 热交换器; 一个泵 和电源。 在正常的电厂运行期间，传热系统可能不连接到核电厂。 电源可以独立于核电站的正常配电系统。 电源可以被配置为为泵供电。 管道系统可以被配置成连接热交换器和泵。 第一和第二连接器可以被配置成将热传递系统连接到核电厂的流体系统。
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6.发明申请公开(公告)号：US20140072089A1
公开(公告)日：2014-03-13
申请号：US13611384
申请日：2012-09-12
IPC分类号： G21C15/00
摘要： A method and apparatus for an alternative cooling system used to cool the suppression pool of a Boiling Water Reactor (BWR) nuclear reactor. The cooling system includes a cooling coil in an isolation condenser located at an elevation that is above the suppression pool. The isolation condenser is connected to the suppression pool via inlet and outlet pipes. The system may provide a natural convection flow of fluids between the suppression pool and the cooling coils to passively cool fluid from the suppression pool without requiring external electrical power.
摘要翻译： 用于冷却沸腾反应堆（BWR）核反应堆的抑制池的替代冷却系统的方法和装置。 冷却系统包括隔离冷凝器中的冷却盘管，位于压缩池上方的高度处。 隔离冷凝器通过入口和出口管连接到抑制池。 该系统可以在抑制池和冷却盘管之间提供流体的自然对流，从而抑制来自抑制池的流体，而不需要外部电力。
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7.发明申请METHOD AND SYSTEM FOR EXTERNAL ALTERNATE SUPPRESSION POOL COOLING FOR A BWR 审中-公开用于BWR的外部替代抑制池冷却的方法和系统公开(公告)号：US20140072088A1
公开(公告)日：2014-03-13
申请号：US13609926
申请日：2012-09-11
IPC分类号： G21C9/00
CPC分类号： G21C15/182 , G21D1/02 , Y02E30/31
摘要： A method and system for external alternate suppression pool cooling for a Boiling Water Nuclear Reactor (BWR) that does not breach the Mark I primary containment. The external cooling system may include a heat sink fluidly coupled to cooling coils surrounding the suppression pool. Cool water may be pumped through the cooling coils without the need for normal plant electrical power, which is ideal during a plant emergency. The cooling system may also be operated and controlled from a remote location to protect the safety of plant personnel.
摘要翻译： 用于沸水核反应堆（BWR）的外部替代抑制池冷却的方法和系统，其不违反Mark I主要容纳物。 外部冷却系统可以包括流体耦合到围绕抑制池的冷却盘管的散热器。 冷水可以通过冷却盘管泵送，而不需要正常的工厂电力，这在工厂紧急情况下是理想的。 冷却系统也可以从远程位置操作和控制，以保护工厂人员的安全。
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公开(公告)号：US10777329B2
公开(公告)日：2020-09-15
申请号：US13340675
申请日：2011-12-30
摘要： A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump.
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9.发明申请公开(公告)号：US20140072086A1
公开(公告)日：2014-03-13
申请号：US13609466
申请日：2012-09-11
申请人： John R. BASS , Robert J. GINSBERG
发明人： John R. BASS , Robert J. GINSBERG
IPC分类号： G21C17/112 , B23P11/00
CPC分类号： G21C17/112 , G21C17/022 , G21C17/035 , G21C19/07 , Y10T29/49826
摘要： A method and system for measuring a temperature and liquid level of water within a Spent Fuel Pool (SFP) of a Light Water Reactor, without using external electrical power. The method and system may use a string of thermocouples attached to a cable and mounted in the spent fuel pool. The thermocouples supply their own power when heated by water that is exposed to the thermocouples within the spent fuel pool. The thermocouples may measure the temperature in the SFP. By measuring the temperature, the liquid water level of the SFP may be inferred by comparing a difference in temperature measurements of the thermocouples, as thermocouples exposed to ambient air will experience a noticeably different temperature from the thermocouples covered by water. The cable (with the thermocouples on one end) may terminate in a location that is remote from the SFP.
摘要翻译： 一种在不使用外部电力的情况下测量轻水反应堆废液池（SFP）内的水温和液面水平的方法和系统。 该方法和系统可以使用连接到电缆并安装在乏燃料池中的一串热电偶。 热电偶在被暴露于乏燃料池内的热电偶的水加热时供电。 热电偶可以测量SFP中的温度。 通过测量温度，可以通过比较热电偶温度测量值的差异来推断SFP的液态水位，因为暴露于环境空气的热电偶将会遇到与水覆盖的热电偶明显不同的温度。 电缆（一端有热电偶）可能会终止于远离SFP的位置。
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10.发明申请METHOD AND SYSTEM FOR A SPENT FUEL POOL LEVEL MEASUREMENT WITHOUT ELECTRICAL POWER 审中-公开没有电力的空燃比液位测量的方法和系统公开(公告)号：US20140072085A1
公开(公告)日：2014-03-13
申请号：US13609399
申请日：2012-09-11
申请人： Robert J. GINSBERG , John R. BASS
发明人： Robert J. GINSBERG , John R. BASS
IPC分类号： G21C17/00
CPC分类号： G21D3/04 , G01F23/167 , G21C17/035 , G21C19/07 , Y02E30/40
摘要： A method and apparatus for measuring a liquid level of a Spent Fuel Pool of a Light Water Reactor without using electrical power. The method and apparatus may use a pressurized gas source connected to tubing or piping that may discharge near the bottom of the Spent Fuel Pool. The system may include a flow meter and throttle valve that may be used to determine a required gas pressure to provide a specified flow rate of gas for known Spent Fuel Pool water levels. By obtaining calibration data points of pressure and flow for multiple Spent Fuel Pool water levels, a calibration curve may be obtained that allows for the measurement of Spent Fuel Pool liquid level using the system, without the need for electrical power.
摘要翻译： 一种用于在不使用电力的情况下测量轻水反应堆废液池的液位的方法和装置。 该方法和装置可以使用连接到可以在废燃料池底部附近放电的管道或管道的加压气体源。 该系统可以包括流量计和节流阀，其可用于确定所需的气体压力以为已知的废油池水位提供指定的气体流量。 通过获得多个废燃料池水位的压力和流量的校准数据点，可以获得允许使用系统测量废燃料池液位而不需要电力的校准曲线。
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