GB/T 40860-2021Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants (English PDF)
压水堆核电厂设计扩展工况分析要求
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Issued by
SAMR; SAC
Level / Type
National · Recommended
Issue date
October 11, 2021
Implementation date
May 1, 2022
Scope
GB/T 40860-2021 is the English-translated version of 压水堆核电厂设计扩展工况分析要求.
GB/T 40860-2021 sets the requirements for the safety analysis of design extension conditions at pressurized water reactor nuclear power plants. It treats the two kinds of design extension condition separately: DEC-A, without significant core damage, and DEC-B, the core melt conditions, that is severe accidents.
For each it gives the acceptance criteria, how the operating conditions to be analysed are selected and the analysis method, and two informative annexes give example lists of DEC-A and DEC-B conditions.
It defines design basis accident, design extension condition, single failure and severe accident. Other reactor types may use it as a reference, but it does not cover the analysis of accident conditions in spent fuel pools. It was issued on 11 October 2021 and has applied since 1 May 2022.
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Document preview — GB/T 40860-2021
National Standard of the People's Republic of China
- ICS
- 27.120.20
- Classification
- F 65
Issued by: State Administration for Market Regulation; Standardization Administration of the PRC
Contents
- Foreword
- 1 Scope
- 2 Normative references
- 3 Terms and definitions
- 4 DEC-A safety analysis requirements
- 4.1 DEC-A acceptance criteria
- 4.2 DEC-A working condition selection
- 4.3 DEC-A analysis method
- 5 DEC-B safety analysis requirements
- 5.1 DEC-B acceptance criteria
- 5.2 DEC-B working condition selection
- 5.3 DEC-B analysis method
- Appendix A (informative) Example of DEC-A list for pressurized water reactor nuclear power plants
- Appendix B (informative) Example of DEC-B list for pressurized water reactor nuclear power plants
- Reference
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.
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; 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 Single failure
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;
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.
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