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GB/T 41140-2021Analysis criterion for radiation source term of reactor core and spent fuel assembly in PWR nuclear power plant (English PDF)

压水堆核电厂堆芯及乏燃料组件辐射源项分析准则

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Issued by

SAMR; SAC

Level / Type

National · Recommended

Issue date

December 31, 2021

Implementation date

July 1, 2022

Scope

GB/T 41140-2021 is the English-translated version of 压水堆核电厂堆芯及乏燃料组件辐射源项分析准则.

GB/T 41140-2021 gives the criteria for analysing the radiation source terms of the reactor core, of spent fuel assemblies and of fuel-related components in pressurized water reactor nuclear power plants.

After the basic requirements it treats the three source terms in turn, and its informative annexes list the nuclides and element types selected for the core inventory analysis and the types of nuclides.

It defines the terms used, among them fuel assembly, fuel-related assembly, activation product, fission product, actinide nuclide and burnup.

Other reactor types, such as heavy water, high-temperature gas-cooled and fast breeder reactors, can use it for reference, but it does not cover the off-reactor storage, transport, reprocessing or disposal of spent fuel. It was issued on 31 December 2021 and has applied since 1 July 2022.

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Document preview — GB/T 41140-2021

National Standard of the People's Republic of China

ICS
27.120
Classification
F 70

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

Contents

  • Preface
  • 1 Scope
  • 2 Normative references
  • 3 Terms and Definitions
  • 4 Basic requirements
  • 5 Core radiation source item
  • 6 Radiation source item of spent fuel assembly
  • 7 Fuel-related components radiation source item
  • Appendix A (Informative) Nuclides and Element Types Selected in the Core Inventory Analysis
  • Appendix B (Informative) Types of Nuclides
  • 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" drafted.

1 Scope

This document specifies the criteria for the analysis of radiation source terms for the core, spent fuel assemblies and fuel-related assemblies of pressurized water reactor nuclear power plants.

This document applies to the radiation source term analysis of the core, spent fuel assemblies and fuel-related assemblies of pressurized water reactor nuclear power plants. Other reactor types (such as heavy water reactor, high temperature gas-cooled reactor, fast breeder reactor, etc.) for reference.

This document does not apply to the off-reactor storage, transportation, reprocessing and disposal of spent fuel.

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 Fuel assembly

A set of fuel elements that are assembled together and not disassembled during core loading and unloading. [Source: GB/T 4960.2-1996, 3.10]

3.2 Fuel associated assembly

A collective term for control rod assemblies, neutron source assemblies, combustible poison assemblies, and resistance plug assemblies. [Source: GB/T 4960.2-1996, 3.13]

3.3 Activation product

A radioactive product produced when neutrons, protons, or other nuclear particles bombard a material. [Source: GB/T 4960.1-2010,7.58]

3.4 Fission product

Fission fragments and their decay products produced by nuclear fission. [Source: GB/T 4960.1-2010,6.13]

3.5 Actinide nuclide

In the periodic table, the nuclides from element 89 actinium to element 103 rhbium. [Source: GB/T 4960.1-2010, 2.87, with modifications]

3.6 Burnup; specific fuel consumption

The energy released per unit mass of primary actinides (eg uranium and plutonium) in a region of a fuel assembly. [Source: GB/T 15146.12-2017, 3.3]

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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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