GB/T 44772-2024Control of contact materials in manufacturing, packaging, storage and transportation of PWR nuclear fuel elements (English PDF)

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 is required.

Please note that some of the contents of this document may involve patents. The issuing organization of this document does not assume the responsibility for identifying patents.

This document was proposed and coordinated by the National Technical Committee for Nuclear Energy Standardization (SAC/TC 58).

This document was drafted by: China National Nuclear Corporation Jianzhong Nuclear Fuel Element Co., Ltd. and China Nuclear Power Research and Design Institute.

The main drafters of this document are: Zhong Duojun, Wu Ping, He Jun, Li Sha, Luo Linling, Dai Jianxiong, Ye Wanyi, and Pu Zengping.

Pressurized water reactor nuclear fuel element manufacturing and packaging, storage, Control requirements for materials in contact with the environment during transportation

1 Scope

This document specifies the classification, requirements and control of contact materials during the manufacture, packaging, storage and transportation of pressurized water reactor nuclear fuel elements. Require.

This document applies to the control of contact materials during the manufacturing, packaging, storage and transportation of pressurized water reactor nuclear fuel assemblies and related components.

The control of contact materials during material manufacturing and its packaging, storage and transportation can be implemented for reference.

2 Normative references

The contents of the following documents constitute the essential clauses of this document through normative references in this document.

For referenced documents without a date, only the version corresponding to that date applies to this document; for referenced documents without a date, the latest version (including all amendments) applies. In this document.

EJ/T 957 Cleanliness and cleaning of pressurized water reactor fuel assemblies EJ/T 1028 Autoclave corrosion test for zirconium and zirconium alloys NB/T 20233 Cleanliness and cleanliness requirements for nuclear steam supply system equipment in pressurized water reactor nuclear power plants

3 Terms and Definitions

The following terms and definitions apply to this document.

4 Classification of contact materials

4.1 According to the degree of influence of contact materials on the quality and final cleanliness of nuclear fuel assemblies and related components, contact materials are divided into non-restricted materials Materials and restricted materials.

4.2 Non-restricted materials generally include.

Austenitic stainless steel; a) Nickel-based alloys; b) Zirconium alloy; c)