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GB/T 42142-2022Analysis criterion for radiation source term in auxiliary and secondary coolant system of pressurized water reactor nuclear power plant (English PDF)

压水堆核电厂辅助系统及二回路系统辐射源项分析准则

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Issued by

SAMR; SAC

Level / Type

National · Recommended

Issue date

December 30, 2022

Implementation date

July 1, 2023

Scope

GB/T 42142-2022 is the English-translated version of 压水堆核电厂辅助系统及二回路系统辐射源项分析准则.

GB/T 42142-2022 sets the methods and assumptions for analysing the radiation source term of the auxiliary systems and the secondary circuit of a pressurised water reactor nuclear power plant under normal operating conditions.

It states that the analysis serves the radiation safety analysis and the shielding design of those systems, that the calculation starts from the primary circuit design source term - itself built on the design basis source term for the design basis cladding damage rate, the transient value of the main coolant source term and the cold shutdown peak - and that process parameters are chosen so the shielding design source term envelops the source terms possible in normal operation.

Appendices list the major nuclides of a typical plant and the estimation parameters. Issued on 30 December 2022, it has applied since 1 July 2023.

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Document preview — GB/T 42142-2022

National Standard of the People's Republic of China

ICS
17.240
Classification
F 74

Issued by: State Administration for Market Regulation; Standardization Administration of the PRC

Contents

  • Preface
  • 1 Scope
  • 2 Normative references
  • 3 Terms and Definitions
  • 4 General
  • 5 General requirements
  • 6 Analysis of Radiation Source Item of Auxiliary System
  • 7 Secondary circuit system radiation source item
  • Appendix A (informative) Major nuclides and their classifications in the auxiliary system and secondary circuit system fluid of a typical PWR nuclear power plant
  • Appendix B (Informative) Estimation Parameter Table

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 for Standardization Documents" drafting.

1 Scope

This document specifies the methods to be followed in the analysis of the radiation source items of the auxiliary system and the secondary circuit system of the pressurized water reactor nuclear power plant under normal operating conditions. and assumptions.

This document is applicable to the analysis of the radiation source item of the auxiliary system and the secondary circuit system of the pressurized water reactor nuclear power plant under normal operating conditions.

2 Normative references

This document has no normative references.

3 Terms and Definitions

The following terms and definitions apply to this document.

3.1 Normal operation

The operation of a nuclear power plant within specified operating limits and conditions.

3.2 Radiant source term

sourceterm The actual or possible release of radiation and (or) radioactive substances and and energy related data.

Note: such as the type, quantity and chemical form of radionuclides.

3.3 Auxiliary system

Support systems and related service systems for reactor coolant systems.

Note: Such as reactor pool, spent fuel pool cooling and processing system, chemical and volume control system, waste heat removal system and waste treatment system, etc.

4 General rules

4.1 The analysis of the radiation source item of the auxiliary system and the secondary circuit system is applicable to the auxiliary system and the secondary circuit system under the normal operating conditions of the PWR nuclear power plant. System-related radiation safety analysis and shielding design.

4.2 When analyzing the radiation source item, the calculation and analysis shall be carried out based on the primary circuit design source item. The primary circuit design source item is based on the design basis source item (ie The primary circuit fission product source item corresponding to the design basis cladding damage rate), the transient value of the main coolant radiation source item and the cold shutdown peak.

4.3 The calculation of system and equipment source items should be based on the operating mode of the system, and the calculation model should be able to truly reflect the system function and process flow.

4.4 The process parameters should be selected according to the principle that the shielding design source term can envelop the different source terms that may occur under normal operating conditions.

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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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