Method and system for calculating and evaluating leakage rate of safety shell of nuclear power plant

A containment and leakage rate technology, applied in the field of nuclear power plants, can solve problems such as low accuracy, inability to judge rationality, and low reliability

Active Publication Date: 2018-11-23
CHINA NUCLEAR POWER DESIGN COMPANY +3
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  • Abstract
  • Description
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  • Application Information

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Problems solved by technology

[0004] The existing technology generally adopts a known leak rate monitoring software to evaluate the calculation of the leak rate. The software defines the calculation method of the type A assessment uncertainty, but it is not the same as the calculation method of the slope

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  • Method and system for calculating and evaluating leakage rate of safety shell of nuclear power plant
  • Method and system for calculating and evaluating leakage rate of safety shell of nuclear power plant
  • Method and system for calculating and evaluating leakage rate of safety shell of nuclear power plant

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Embodiment 1

[0074] An embodiment of the present invention provides a method for calculating and evaluating the containment leakage rate of a nuclear power plant, such as figure 1 As shown, the method includes:

[0075] S1. Obtain the Type A assessment uncertainty of the containment leakage rate calculation;

[0076] S2. According to the real-time measurement data of the sensors in the containment, obtain the B-type evaluation uncertainty for the calculation of the containment leakage rate;

[0077] S3. Combining the Type A assessment uncertainty and the Type B assessment uncertainty into a containment leak rate uncertainty, so as to evaluate the calculation of the containment leak rate according to the containment leak rate uncertainty.

[0078] It should be noted that during the operation of the unit, the containment leakage rate of the nuclear power plant needs to be monitored in real time to monitor the change of containment sealing, and the monitoring of the containment leakage rate ...

Embodiment 2

[0177] The embodiment of the present invention provides a nuclear power plant containment leakage rate calculation and evaluation system, which can realize all the processes of the nuclear power plant containment leakage rate calculation and evaluation method, such as figure 2 As shown, the system includes:

[0178] Type A evaluation uncertainty acquisition module 1, used to obtain type A evaluation uncertainty for calculating containment leakage rate;

[0179] Type B assessment uncertainty acquisition module 2, which is used to obtain the Type B assessment uncertainty for calculating the containment leakage rate according to the real-time measurement data of the sensors in the containment;

[0180] Synthetic assessment module 3, used for synthesizing the type A assessment uncertainty and the type B assessment uncertainty into the containment leak rate uncertainty, so as to calculate the containment leak rate according to the containment leak rate uncertainty calculations ar...

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Abstract

The invention discloses a method for calculating and evaluating the leakage rate of safety shell of a nuclear power plant, comprising the following steps of: obtaining uncertainty of a class A assessment for calculating the leakage rate of safety shell; obtaining uncertainty of a class B assessment for calculating the leakage rate of safety shell according to the real time measured data of the sensors in the safety shell; and synthesizing the uncertainty of the class A assessment and the uncertainty of the class B assessment into a uncertainty of the leakage rate of safety shell to evaluate calculation of the leakage rate of safety shell according to the uncertainty of the leakage rate of safety shell. The invention also discloses a system for calculating and evaluating leakage rate of safety shell of nuclear power plant. According to the method and system for calculating and evaluating the leakage rate of safety shell of a nuclear power plant, the reliability and accuracy of the evaluation can be improved.

Description

technical field [0001] The invention relates to the technical field of nuclear power plants, in particular to a method and system for calculating and evaluating the containment leakage rate of a nuclear power plant. Background technique [0002] The mass conservation method is commonly used in the world to calculate the containment leakage rate. According to the ideal gas state equation, the standard volume of air (the volume at 0, ℃ 1.01325×105Pa) is equivalent to the air mass, and several standard volume changes DV in one day are used. H Linear fitting with time, the slope of the line is the leakage rate Q of the day ld . Containment leak rate Q ld Characterized by its best estimated value and uncertainty, the uncertainty of containment leak rate is an important index to measure the reliability of leak rate calculation results. [0003] In statistics, the uncertainty of containment leakage rate is composed of Type A assessment uncertainty and Type B assessment uncertain...

Claims

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Application Information

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IPC IPC(8): G06Q10/06G06Q50/06
CPCG06Q10/0635G06Q10/06393G06Q50/06
Inventor 孙瑜田骏李天友刘肇阳闫蔚
Owner CHINA NUCLEAR POWER DESIGN COMPANY
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