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A Quantitative Analysis Method and System for Nuclear Power Plant Accident Regulations

An analysis method and technology for nuclear power plants, applied in nuclear power plants, nuclear power plant control, nuclear engineering, etc., can solve problems such as lack of sub-program support evaluation, initial causes of accidents, and limitation of fault types.

Active Publication Date: 2022-05-13
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, at present, the development of accident procedures in nuclear power plants will also carry out supporting evaluations, but the selected initial causes of accidents and failure types are relatively limited, and only relatively typical accidents or failures are considered. On the other hand, the analysis of the supporting evaluation of the existing procedures is mainly from the perspective of primary cause, and lacks the supporting evaluation from the dimension of sub-procedures

Method used

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  • A Quantitative Analysis Method and System for Nuclear Power Plant Accident Regulations
  • A Quantitative Analysis Method and System for Nuclear Power Plant Accident Regulations
  • A Quantitative Analysis Method and System for Nuclear Power Plant Accident Regulations

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Embodiment 1

[0046] like Figure 1 to Figure 4 As shown, the present invention is a quantitative analysis method for nuclear power plant accident regulations, such as figure 1 As shown, the method includes the following steps:

[0047] S1: Use different levels of working condition selection methods to obtain the working condition spectrum for quantitative evaluation of accident procedures;

[0048] S2: Construct a two-dimensional quantitative evaluation system model according to the obtained working condition spectrum of the quantitative evaluation of accident procedures; the two-dimensional quantitative evaluation system model includes an evaluation system model based on the initial cause event dimension and an evaluation based on the sub-procedure dimension system model;

[0049] S3: Obtain the quantitative analysis requirements of nuclear power plant accident procedures, and automatically select the evaluation system model of the corresponding dimension to perform quantitative analysi...

Embodiment 2

[0091] like Figure 1 to Figure 4 As can be seen, the difference between this embodiment and Embodiment 1 is that this embodiment takes the type of accident "there is a breach of isolation failure on the secondary side of the steam generator" as an example to illustrate the implementation of the quantitative analysis method for the corresponding accident regulations process.

[0092] (1) First, in the process of determining the evaluation work spectrum, through the attached figure 2 The process shown can be obtained:

[0093] (a) A single breach at different positions on the secondary side of the steam generator;

[0094] (b) breaches leading to uncontrolled pressure relief on the secondary side of all steam generators;

[0095] (c) The steam generator breach where the heat transfer tube of the superimposed steam generator is broken;

[0096] Among them, the breach in item (b) is the breach of isolation failure of the secondary side of the steam generator.

[0097] (2) S...

Embodiment 3

[0105] like Figure 1 to Figure 5 As shown, the difference between this embodiment and Embodiment 1 is that this embodiment provides a quantitative analysis system for nuclear power plant accident regulations, such as Figure 5 As shown, the system includes:

[0106] Obtaining the working condition spectrum unit, which is used to adopt different levels of working condition selection methods to obtain the working condition spectrum for quantitative evaluation of accident procedures;

[0107] Constructing an evaluation system unit for constructing a two-dimensional quantitative evaluation system model based on the acquired working condition spectrum for quantitative evaluation of accident procedures; the two-dimensional quantitative evaluation system model includes an evaluation system model based on the initial cause event dimension and a The evaluation system model of the sub-procedure dimension;

[0108] The quantitative analysis unit is used to obtain the quantitative anal...

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Abstract

The invention discloses a quantitative analysis method and system for nuclear power plant accident procedures. The method includes: S1: adopting different levels of working condition selection methods to obtain a working condition spectrum for quantitative evaluation of accident procedures; S2: according to the acquired accident procedures Quantitative evaluation of the working condition spectrum, constructing a two-dimensional quantitative evaluation system model, including the evaluation system model based on the primary event dimension and the evaluation system model based on the sub-procedure dimension; S3: Obtain the quantitative analysis requirements of nuclear power plant accident procedures, according to According to the requirements, the evaluation system model of the corresponding dimension is automatically selected for quantitative analysis of the nuclear power plant accident regulations, and the quantitative analysis results are obtained; and then the nuclear power plant is gradually guided to the expected state. The present invention conducts all-round quantitative analysis on the accident procedure from different angles, and the analysis and evaluation are effective, thereby providing a powerful theoretical basis for the design, demonstration and optimization of the accident procedure.

Description

technical field [0001] The invention relates to the technical field of pressurized water reactor nuclear power plant accident regulations, in particular to a quantitative analysis method and system for nuclear power plant accident regulations. Background technique [0002] The regulations of nuclear power plants mainly include normal operation procedures, abnormal operation procedures, accident emergency procedures (ie accident procedures) and severe accident management guidelines. Among them, accident procedures mainly deal with those events or accidents that lead to emergency shutdown and / or activation of special safety systems, and have not yet reached a serious accident state. Usually, accident procedures will provide execution items such as accident diagnosis, fault handling, nuclear power plant status maintenance and recovery, etc. Operators will operate according to the specific information given by accident procedures to guide the nuclear power plant to the expected ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00G21D3/00G21D3/04G21D3/06
CPCG21C17/001G21D3/06G21D3/04G21D3/002Y02E30/00Y02E30/30
Inventor 喻娜冉旭吴清刘昌文冷贵君李峰丁书华鲜麟陈伟陈宏霞吴丹钱立波杨帆周科吴鹏初晓蔡容张舒习蒙蒙陆雅哲程坤杨韵佳
Owner NUCLEAR POWER INSTITUTE OF CHINA