Large break loss-of-water accident analysis method and system

A water loss accident and analysis method technology, which is applied in special data processing applications, computer-aided design, design optimization/simulation, etc. Efficiency, shorten the evaluation cycle, reduce the effect of human error rate

Pending Publication Date: 2021-10-22
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
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  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The purpose of the present invention is to provide a method and system for analyzing the loss of water accidents of large grooves, so as to solve the problems of low analysis efficiency and human errors in the analysis process of large groove loss of water accidents

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  • Large break loss-of-water accident analysis method and system

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Embodiment Construction

[0026] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0027] A method for analyzing a large breach loss of water accident, the method specifically includes the following steps:

[0028] S1. Select the index parameters related to the large breach loss of water accident of the nuclear power plant, and conduct a sample sampling of each parameter to check the parameter distribution to verify the validity of the parameter sample value;

[0029] Analyze the conservative assumptions, parameters, parameter ranges and distribution forms of the initial conditions and boundary conditions related to the large breach loss of water accident of the nuclear power plant, and input the above information into the formulated input text in JSON format, wherein the formulated input text Sampling parameters include parameters that have a greater impact on PCT under loss of fluid accidents, including but not li...

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Abstract

The invention relates to the technical field of reactor thermal hydraulic design and safety analysis, and particularly discloses a large-break water loss accident analysis method and system. The method includes following steps: selecting index parameters related to the nuclear power plant large crevasse water loss accident; establishing a steady-state calculation model, performing steady-state calculation on the related parameters of the large break water loss accident, and performing parameter value verification after the steady-state calculation; establishing a transient calculation model and carrying out transient calculation on related parameters of the large crevasse water loss accident, performing comparison with actual crevasse and nuclear power plant external power conditions according to a calculation result, and when deviation occurs, reconstructing the transient calculation model and performing transient calculation; and performing safe water injection deduction to obtain a liquid level parameter value, updating the transient model, performing recalculation on the basis of a steady-state calculation result, and performing parameter display and analysis after calculation is completed. According to the method and the system, the problems of multiple working conditions, complicated process and high human error rate of pressurized water reactor large break water loss accident analysis are solved.

Description

technical field [0001] The invention belongs to the technical field of thermal-hydraulic design and safety analysis of reactors, and in particular relates to an analysis method and system for a large breach loss-of-water accident. Background technique [0002] Large breach accidents determine one of the most important design basis accidents for the operating power of nuclear power plants, and its analysis and evaluation models can be selected from conservative evaluation models, combined evaluation models, best estimation models, and risk-guided evaluation models. These models mainly include computer programs, system component availability assumptions, initial conditions and boundary conditions. When the computer program adopts the system program of the Appendix K model that meets the requirements of the regulations, the availability of system components adopts conservative assumptions, and the initial conditions and boundary conditions adopt actual data + uncertainties, a c...

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/20G06F119/08
CPCG06F30/20G06F2119/08
Inventor 黄涛邓坚李仲春丁书华李庆冷贵君刘余卢宗健钱立波吴丹陈伟申亚欧马海福张曌寰
Owner NUCLEAR POWER INSTITUTE OF CHINA
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