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GB/T 40860-2021 English PDF

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GB/T 40860-2021: Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants
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Basic data

Standard ID GB/T 40860-2021 (GB/T40860-2021)
Description (Translated English) Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants
Sector / Industry National Standard (Recommended)
Classification of Chinese Standard F65
Word Count Estimation 10,175
Issuing agency(ies) State Administration for Market Regulation, China National Standardization Administration

GB/T 40860-2021: Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants


---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants ICS 27.120.20 CCSF65 National Standards of People's Republic of China Analysis requirements for design expansion of pressurized water reactor nuclear power plants Released on 2021-10-11 2022-05-01 implementation State Administration of Market Supervision and Administration Issued by the National Standardization Management Committee

Table of contents

Foreword Ⅰ 1 Scope 1 2 Normative references 1 3 Terms and definitions 1 4 DEC-A safety analysis requirements 1 4.1 DEC-A acceptance criteria 1 4.2 DEC-A working condition selection 2 4.3 DEC-A analysis method 2 5 DEC-B safety analysis requirements 3 5.1 DEC-B acceptance criteria 3 5.2 DEC-B working condition selection 3 5.3 DEC-B analysis method 3 Appendix A (informative) Example of DEC-A list for pressurized water reactor nuclear power plants 5 Appendix B (informative) Example 6 of DEC-B list for pressurized water reactor nuclear power plants Reference 7

Foreword

This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for Standardization Work Part 1.Structure and Drafting Rules of Standardization Documents" Drafting. Please note that some of the contents of this document may involve patents. The issuing agency of this document is not responsible for identifying patents. This document was proposed and managed by the National Nuclear Energy Standardization Technical Committee (SAC/TC58). Drafting organizations of this document. China Nuclear Power Engineering Co., Ltd., China Nuclear Power Research and Design Institute, China General Nuclear Power Engineering Co., Ltd. The main drafters of this document. Xing Ji, Lu Yili, Sun Jinlong, Huang Daishun, Huang Weifeng, Yuan Xia, Chen Qiaoyan, Lu Wenkui, Yu Na, Yu Xinli, Zhang Ming, Yang Changjiang, Qiu Zhifang, Deng Wei, Fang Hongyu, Wang Hui, Deng Chunrui, Ma Chao, Li Haiying, Zhan Jingxiang, Wei Wei, Shi Xueyao, Zhu Zengpei, Huang Huan, Xu Weifeng. Analysis requirements for design expansion of pressurized water reactor nuclear power plants

1 Scope

This document specifies the requirements for safety analysis of PWR nuclear power plant design extension conditions, including acceptance criteria, selection of operating conditions, analysis methods, etc. This document is applicable to the safety analysis of PWR nuclear power plant design expansion conditions, and other reactor-type nuclear power plants are used as reference. This document does not include relevant requirements for analysis of accident conditions of spent fuel pools.

2 Normative references

There are no normative references in this document.

3 Terms and definitions

The following terms and definitions apply to this document. 3.1 Design basis accident designbasisaccident; DBA Assuming accidents that lead to accidental conditions of nuclear power plants, the release of radioactive materials in these accidents is within acceptable limits. Set design criteria and conservative methods to design. [Source. HAF102-2016, noun explanation] 3.2 Design extension condition; DEC Accident conditions that are not within the scope of the design basis accident are considered in the design process according to the best estimation method, and the accident The release of radioactive materials in the current situation is within acceptable limits. Note. Design extension conditions include design extension conditions (DEC-A) and core melting conditions (ie serious accidents, DEC-B) that did not cause significant damage to the core. [Source. HAF102-2016, noun explanation, modified] 3.3 Singlefailure A failure that causes a single system or component to fail to perform its predetermined safety function, and various subsequent failures caused by this. [Source. HAF102-2016, noun explanation] 3.4 Severe accident An accident condition whose severity exceeds the design basis accident and causes significant deterioration of the core. [Source. HAF102-2016, noun explanation] 4 DEC-A safety analysis requirements 4.1 DEC-A acceptance criteria The acceptance criteria used in DEC-A analysis include. a) The core should finally reach and be in a subcritical state, and the residual heat of the reactor should be effectively discharged;

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