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。

公开(公告)号：US12183474B2

公开(公告)日：2024-12-31

申请号：US17454196

申请日：2021-11-09

Applicant: Westinghouse Electric Company LLC

Inventor： Edward J. Lahoda ,  Frank A. Boylan ,  Ho Q. Lam ,  Mitchell E. Nissley ,  Raymond E. Schneider ,  Robert L. Oelrich ,  Sumit Ray ,  Radu Pomirleanu ,  Zeses Karoutas ,  Michael J. Hone

IPC: G21C7/10 ,  G21C7/24 ,  C23C30/00 ,  G21C1/08 ,  G21C3/07 ,  G21C3/328 ,  G21C11/08

Abstract: A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.

公开(公告)号：US11289213B2

公开(公告)日：2022-03-29

申请号：US16051712

申请日：2018-08-01

Applicant: WESTINGHOUSE ELECTRIC COMPANY LLC

Inventor： Edward J. Lahoda ,  Frank A. Boylan ,  Ho Q. Lam ,  Mitchell E. Nissley ,  Raymond E. Schneider ,  Robert L. Oelrich ,  Sumit Ray ,  Radu Pomirleanu ,  Zeses Karoutas ,  Michael J. Hone

IPC: G21C7/24 ,  G21C7/10 ,  G21C3/07 ,  G21C1/08 ,  G21C11/08 ,  G21C3/328 ,  C23C30/00

Abstract: A control rod for a nuclear fuel assembly is described herein that includes a neutron absorbing material having a melting point greater than 1500° C. that does not form a eutectic with a melting point less than 1500° C., and may further include a cladding material having a melting point greater than 1500° C. The cladding material is selected from the group consisting of silicon carbide, zirconium, a zirconium alloy, tungsten, and molybdenum. The absorbing material is selected from the group consisting of Gd2O3, Ir, B4C, Re, and Hf. The metal cladding or the absorbing material may be coated with an anti-oxidation coating of Cr with or without a Nb intermediate layer.