A mutual calibration method for core water level and subcooling margin channel

A technology of supercooling margin and core water level, applied in the fields of reactors, nuclear reactor monitoring, nuclear power generation, etc., can solve the problems of inconsistent data, obstacles to operator procedure selection, and increasing accuracy requirements.

Active Publication Date: 2016-01-27
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
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  • Application Information

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Problems solved by technology

However, with the gradual maturity and extensive application of State-Oriented Procedures (SOP), operators are increasingly relying on the core cooling status information provided by the core minimum subcooling margin and water level to make procedure judgments. The accuracy of temperature and water level monitoring data is getting higher and higher, and data inconsistency in redundant series should be avoided, otherwise it will bring obstacles to the operator's selection of procedures and affect the safety of the power plant

Method used

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Embodiment Construction

[0091] The present invention comprises the following steps in turn:

[0092] Step 1. Obtain the measurement data of series A and B;

[0093] The following parameters are obtained through A series of measurements:

[0094] -Number of main pumps currently in normal operation RCP-A ;

[0095] - Minimum core supercooling margin ΔT SAT-A ;

[0096] - Core minimum subcooling margin validity state SΔT SAT-A ;1 means valid, 0 means invalid;

[0097] -Uncertainty of core minimum subcooling margin ΣΔT SAT-A ;

[0098] - Reactor pressure vessel water level L VSL-A ;

[0099] - Reactor Pressure Vessel Water Level Validity Status SL VSL-A ;

[0100] The following parameters are obtained through B series measurement;

[0101] -Number of main pumps currently in normal operation RCP-B ;

[0102] - Minimum core supercooling margin ΔT SAT-B ;

[0103] - Core minimum subcooling margin validity state SΔT SAT-B ;1 means valid, 0 means invalid;

[0104] -Uncertainty of core minimum ...

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Abstract

The invention relates to a crosscheck method for core water level and supercooling margin channel. Based on crosschecking on a lowest supercooling margin of a core and series data combination of uncertainty and redundancy of a measure channel for water level of a reactor pressure vessel, and a physical possible region, the method employs steps, including acquisition of measured data of A, B series, judgment on crosschecking startup conditions, statistics of signal validity status and preliminary calculation, judgment on theoretical consistency, and data check calculation, to finally process measured data of A and B series into a single most credible group of data of the lowest core supercooling margin and the water level of the pressure vessel, so as to improve the data reliability, simplify the number of interfaces for an operator, and at the same time avoid the situation that the operator can not carry out processing when encountering inconsistency of the A and B series data.

Description

technical field [0001] The invention relates to a method for mutual calibration of core water level and supercooling margin channel, in particular to a method for mutual calibration of core water level and supercooling margin channel in the field of nuclear power plant post-accident monitoring system data processing. Background technique [0002] According to literature retrieval, "Design of Core Cooling Monitoring System for Phase II Expansion Project of Qinshan Nuclear Power Plant" published in "Nuclear Power Engineering" 2008 Vol.29No.1, pages 5-9, is relatively close to the present invention. [0003] In conventional event-oriented procedures (EOP)-based power plants, the minimum subcooling margin of the reactor core and the reactor pressure vessel water level measurement system are designed based on experience feedback after the Three Mile Island accident. After the Three Mile Island accident, in order to know the minimum supercooling margin of the core and the change t...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 李小芬苟拓何正熙余俊辉李白王远兵王华金
Owner NUCLEAR POWER INSTITUTE OF CHINA
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