公开(公告)号：US20140270040A1

公开(公告)日：2014-09-18

申请号：US13908153

申请日：2013-06-03

Applicant: Westinghouse Electric Company LLC

Inventor： HO Q. LAM ,  Vefa N. Kucukboyaci ,  Yung-An Chao ,  Robert W. Flammang ,  William H. Slagle ,  Patrick J. Sebastiani

IPC: G01T3/00 ,  G01T3/08

CPC classification number: G01T3/08 ,  G21C17/108 ,  G21C19/07 ,  G21C19/40

Abstract: A system and method for measuring and monitoring axial flux to determine subcriticality in a spent fuel pool of a nuclear power plant. In certain embodiments of this invention, one or more neutron detectors are operable to generate signals resulting from neutron interactions in the spent fuel pool, a counting device counts the signals which are generated by the one or more neutron detectors, a connecting means electrically connects the one or more neutron detectors to the counting device, a signal analyzer is used to determine reactivity of the fuel assemblies in the spent fuel pool based on the counted signals, a power supply provides power for the neutron detectors, the counting device and the system analyzer, and a software code containing an axial flux curve index is used to correlate the counted signals to determine the subcriticality of the spent fuel pool.

Abstract translation: 一种用于测量和监测轴向通量以确定核电厂乏燃料池中的亚临界的系统和方法。 在本发明的某些实施例中，一个或多个中子检测器可操作地产生由乏燃料池中的中子相互作用产生的信号，计数装置对由一个或多个中子检测器产生的信号进行计数，连接装置将 一个或多个中子探测器到计数装置，信号分析仪用于根据计数的信号确定燃料组件在乏燃料池中的反应性，电源为中子探测器，计数装置和系统分析仪提供电力 ，并且使用包含轴向通量曲线指数的软件代码来相关联的计数信号以确定乏燃料池的亚临界。

公开(公告)号：US20140241484A1

公开(公告)日：2014-08-28

申请号：US13778565

申请日：2013-02-27

Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC

Inventor： Jun Liao ,  Vefa N. Kucukboyaci

IPC: G21C9/004

CPC classification number: G21C9/004 ,  G21C1/086 ,  G21C1/322 ,  G21C15/18 ,  Y02E30/32

Abstract: A passive cooling system of a pressurized water reactor that relies on a depressurization system to reduce the pressure in the reactor vessel in the event of a loss of coolant accident and vent the steam generated by the decay heat of the reactor core in a post loss of coolant accident stage. The depressurization results in a low pressure difference between the reactor vessel and the containment and enables gravity driven cooling system injection into the reactor vessel. The depressurization system includes a flow restrictor within an orifice in the reactor vessel wall that connects to a vent pipe which forms a flow path between the interior of the reactor vessel and the containment atmosphere when a valve within the vent pipe is in an open position. Preferably, the flow restrictor is a venturi that has a gradual contraction and a gradual expansion in the flow path area.

Abstract translation: 压缩水反应堆的被动冷却系统，其依赖于减压系统以在冷却剂事故损失的情况下降低反应堆容器中的压力，并且在反应堆堆芯的后损失中排出由反应堆堆芯的衰变热产生的蒸汽 冷却液事故阶段。 减压导致反应堆容器和容器之间的低压差，并使重力驱动冷却系统注入反应器容器。 减压系统包括在反应器容器壁中的孔内的限流器，其连接到排气管，该排气管在通气管内的阀处于打开位置时形成反应容器内部和容纳气氛之间的流动路径。 优选地，限流器是文氏管，其在流动通道区域中具有逐渐收缩和逐渐膨胀。

公开(公告)号：US09423516B2

公开(公告)日：2016-08-23

申请号：US13908153

申请日：2013-06-03

Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC

Inventor： Ho Q. Lam ,  Vefa N. Kucukboyaci ,  Yung-An Chao ,  Robert W. Flammang ,  William H. Slagle ,  Patrick J. Sebastiani

IPC: G21C19/40 ,  G01T3/08 ,  G21C17/108 ,  G21C19/07

CPC classification number: G01T3/08 ,  G21C17/108 ,  G21C19/07 ,  G21C19/40

Abstract: A system and method for measuring and monitoring axial flux to determine subcriticality in a spent fuel pool of a nuclear power plant. In certain embodiments of this invention, one or more neutron detectors are operable to generate signals resulting from neutron interactions in the spent fuel pool, a counting device counts the signals which are generated by the one or more neutron detectors, a connecting means electrically connects the one or more neutron detectors to the counting device, a signal analyzer is used to determine reactivity of the fuel assemblies in the spent fuel pool based on the counted signals, a power supply provides power for the neutron detectors, the counting device and the system analyzer, and a software code containing an axial flux curve index is used to correlate the counted signals to determine the subcriticality of the spent fuel pool.

Abstract translation: 一种用于测量和监测轴向通量以确定核电厂乏燃料池中的亚临界的系统和方法。 在本发明的某些实施例中，一个或多个中子检测器可操作地产生由乏燃料池中的中子相互作用产生的信号，计数装置对由一个或多个中子检测器产生的信号进行计数，连接装置将 一个或多个中子探测器到计数装置，信号分析仪用于根据计数的信号确定燃料组件在乏燃料池中的反应性，电源为中子探测器，计数装置和系统分析仪提供电力 ，并且使用包含轴向通量曲线指数的软件代码来相关联的计数信号以确定乏燃料池的亚临界。