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Nuclear power station nuclear island valve leakage monitoring system and method

A technology for monitoring systems and nuclear power plants, applied in measuring devices, measuring heat, testing fluid tightness, etc., can solve the problems of main system leakage, valve monitoring of leakage monitoring, and inability to accurately locate valve leakage, so as to avoid checking leakage, Increased availability, improved reliability, and the effect of accuracy

Pending Publication Date: 2022-02-18
CNNC NUCLEAR POWER OPERATION MANAGEMENT
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

Nuclear power plant nuclear island valve regulator spray valve regulating valve XRCP001VP, XRCP002VP, reactor coolant loop downstream temperature measurement bypass isolation valve XRCP102VP, XRCP202VP, XRCP302VP, reactor coolant loop downstream temperature measurement bypass isolation valve XRCP103VP, XRCP203VP , XRCP303VP, these 8 valves have no leakage monitoring means, so it is impossible to accurately locate the valve leakage
During power operation, if the leakage rate of the main system increases and the liquid level of the pressure relief tank rises, it is impossible to monitor the valves in the nuclear island building without increased leakage monitoring, which may cause an unplanned shutdown to check the leakage of the main system

Method used

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  • Nuclear power station nuclear island valve leakage monitoring system and method
  • Nuclear power station nuclear island valve leakage monitoring system and method
  • Nuclear power station nuclear island valve leakage monitoring system and method

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Embodiment Construction

[0031] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0032] The present invention provides a nuclear power plant nuclear island valve leakage monitoring system, comprising a temperature sensor 4 and a DCS system installed on the nuclear power plant nuclear island valve leakage pipe 1;

[0033] The temperature sensor 4 is used to measure the fluid temperature in the leakage pipe 1 of the nuclear island valve of the nuclear power plant, and send the temperature signal to the DCS system in real time;

[0034] The DCS system receives the temperature signal sent by the temperature sensor in real time, and judges whether the nuclear island valve of the nuclear power plant leaks.

[0035] Further, the type selection and installation method of the temperature sensor 4 are determined according to the specifications, dimensions, parameters and feasibility of the nuclear island valve leakage pipe ...

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Abstract

The invention particularly relates to a nuclear power station nuclear island valve leakage monitoring system. The system comprises a temperature sensor and a DCS system which are installed on a nuclear power station nuclear island valve leakage leading pipe, the temperature sensor is used for measuring the temperature of fluid in the nuclear power station nuclear island valve leakage leading pipe and sending a temperature signal to the DCS system in real time; and the DCS system receives the temperature signal sent by the temperature sensor in real time and judges whether a nuclear island valve of a nuclear power station leaks or not. According to the nuclear power station nuclear island valve leakage monitoring system and method, the leakage condition of the nuclear island valve of the nuclear power station is monitored in real time, the reliability and accuracy of valve leakage monitoring are greatly improved, the non-planned shutdown leakage checking is avoided, and the availability of the power station is improved.

Description

technical field [0001] The invention relates to the technical field of nuclear power plant nuclear island valve leakage monitoring, in particular to a nuclear power plant nuclear island valve leakage monitoring system and method. Background technique [0002] In order to make the nuclear power plant meet the operating technical specifications, it is necessary to monitor the relevant parameters in accordance with the supervision requirements of the "Supervision Program for Periodic Tests of Safety-Related Systems and Equipment" to ensure that all safety-related systems and equipment are available and their performance is correct. Also ensure that all safety limits related to the three barriers are met. Reactor coolant system leaks are continuously monitored by performing the Reactor Coolant System Tightness Test and measuring reactor coolant system leaks (both identifiable and unidentifiable leaks) on a daily basis. If the leakage exceeds the standard (>2300L / h), it is ne...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01M3/00G01K13/00G01K1/024
CPCG01M3/002G01K13/00G01K1/024
Inventor 陈长山雷夏生胡恒清周志文金舟锴王公展王江杰钱敏夏德莉朱静张烨徐精卫沈屹
Owner CNNC NUCLEAR POWER OPERATION MANAGEMENT