Looking for breakthrough ideas for innovation challenges? Try Patsnap Eureka!

A method and system for calculating and evaluating the containment leakage rate of a nuclear power plant

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

Active Publication Date: 2021-12-03
CHINA NUCLEAR POWER DESIGN COMPANY +3
View PDF2 Cites 0 Cited by
  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

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 uncertainty specified in statistics. Inconsistency, cannot judge its rationality, resulting in low reliability of this evaluation method
For Type B evaluation standard uncertainty, the software directly gives a fixed value, resulting in low accuracy of this evaluation method

Method used

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
View more

Image

Smart Image Click on the blue labels to locate them in the text.
Viewing Examples
Smart Image
  • A method and system for calculating and evaluating the containment leakage rate of a nuclear power plant
  • A method and system for calculating and evaluating the containment leakage rate of a nuclear power plant
  • A method and system for calculating and evaluating the containment leakage rate of a nuclear power plant

Examples

Experimental program
Comparison scheme
Effect test

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...

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

PUM

No PUM Login to View More

Abstract

The invention discloses a method for calculating and evaluating the containment leakage rate of a nuclear power plant. category assessment uncertainty; the category A assessment uncertainty and the category B assessment uncertainty are synthesized into the containment leakage rate uncertainty, so as to Compute for evaluation. The invention also discloses a calculation and evaluation system for the containment leakage rate of the nuclear power plant. The invention can improve the reliability and accuracy of evaluation.

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

the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More

Application Information

Patent Timeline
no application Login to View More
Patent Type & Authority Patents(China)
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
Who we serve
  • R&D Engineer
  • R&D Manager
  • IP Professional
Why Patsnap Eureka
  • Industry Leading Data Capabilities
  • Powerful AI technology
  • Patent DNA Extraction
Social media
Patsnap Eureka Blog
Learn More
PatSnap group products