GB/T 16702.8-2025Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 8: Low pressure or atmospheric storage tanks (English PDF)
压水堆核电厂核岛机械设备设计规范 第8部分:低压或常压储罐
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Issued by
State Administration for Market Regulation; Standardization Administration of China
Level / Type
National · Recommended
Issue date
February 28, 2025
Implementation date
February 28, 2025
Scope
GB/T 16702.8-2025 is the English-translated version of 压水堆核电厂核岛机械设备设计规范 第8部分:低压或常压储罐.
GB/T 16702.8-2025 is the Chinese national standard on design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - part 8: low pressure or atmospheric storage tanks, in the field of energy and heat transfer engineering. The /T suffix marks it as a recommended standard: it is not compulsory by itself, but it becomes binding as soon as a contract, a tender or a customer specification calls it up - which in practice is how most foreign buyers meet it. It was issued on 28 February 2025 by the State Administration for Market Regulation; Standardization Administration of China, and has been in force since 28 February 2025. Classification: ICS 27.120.20, CCS F 69. This page is published from the official record of the standard held by the Chinese standards administration: the identification, the dates, the classification and the issuing body are taken from there. The clause text, the tables and the numeric limits are in the document itself, which is delivered complete in English translation.
Document preview — GB/T 16702.8-2025
National Standard of the People's Republic of China
- ICS
- 27.120.20
- Classification
- F 69
Issued by: State Administration for Market Regulation; Standardization Administration of China
Contents
- 1 Scope1
- 2 Normative references1
- 3 Terms and Definitions1
- 4 Symbols1
- 5 Basic Requirements2
- 5.1 Scope of application of storage tanks2
- 5.2 Boundary between tank and foundation3
- 5.3 Boundaries between tanks and pipelines3
- 5.4 Tank classification3
- 5.5 Required Documents3
- 5.6 Identification4
- 5.7 Weld seam marking5
- 6 Materials6
- 6.1 General6
- 6.2 Supplementary Provisions6
- 7 Design6
- 7.1 General Design Rules6
- 7.2 Design Rule10
- 8 Manufacturing and inspection32
- 8.2 Identification32
- 8.3 Cut32
- 8.4 Non-welding repair32
- 8.5 Welding repair33
- 8.6 Forming33
- 8.7 Grouping of parts33
- 8.8 Welding and related technologies33
- 8.9 Weld inspection37
- 9 Test43
- 9.1 Check43
- 9.2 Test43
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. This document is Part 8 of GB/T 16702 "Design Specifications for Mechanical Equipment of Nuclear Island in Pressurized Water Reactor Nuclear Power Plant". The following parts are published.
2.Class 1 equipment;
3.Level 2 equipment;
4.Level 3 equipment;
5.Small equipment;
6.Reactor internals;
7.Equipment support;
8.Low-pressure or atmospheric pressure storage tanks. This document replaces Chapter 11 of GB/T 16702-2019 "Design Specifications for Mechanical Equipment of Nuclear Island of Pressurized Water Reactor Nuclear Power Plants" Compared with Chapter 11 of GB/T 16702-2019, in addition to structural adjustments and editorial changes, the main technical changes are as follows:
--- Changed the chemical composition part, increased the S and P content requirements, changed from "w(S)<=0.040%; w(P)<=0.040%" to "S content <= 0.015%; P content <= 0.025%" (see 6.2.1.1, 11.2.2.1.1 of the.2019 edition). 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 Nuclear Energy Standardization Technical Committee (SAC/TC58). This document was drafted by: China Nuclear Power Research and Design Institute, China Nuclear Power Engineering Co., Ltd., Shanghai Nuclear Engineering Research and Design Institute Co., Ltd. Co., Ltd., China General Nuclear Power Engineering Co., Ltd., Nuclear and Radiation Safety Center of the Ministry of Ecology and Environment, China Machinery Productivity Promotion Center, Nuclear Industry Standardization Research Institute Research Institute. The main drafters of this document are. Li Donghui, Yuan Hong, Sun Yingxue, Weng Chenyang, Tian Jun, Meng Xianggai, Tang Chenhang, Fu Guanhua, Huang Zongren, Fu Xiaolong, He Jinsong, Yang Chuansheng, Huang Hai, He Gongning, Liu Wenjin, Zeng Zhongxiu, Wei Wei, Wang Zhonghui, Feng Zhipeng, Zuo Shuchun, Zheng Yue, Dong An, Tian Jinmei, Yu Shunli, Fan Zhang, Jin Wenjuan, Li Chuanyi, Shen Rui, Wu Chongzhi, Weng Zhimin, Zhang Xinghui, Ou Guoyong, Wen Jing, Li Hailong, Pan Jun, Li Yingke, Wu Feifei, Liang Yun. The previous versions of this document and the documents it replaces are as follows:
---First published in.1996 as GB/T 16702-1996, first revised in.2019;
GB/T 16702 "Design Specification for Mechanical Equipment of Nuclear Island of Pressurized Water Reactor Nuclear Power Plant" is a general technical specification for the design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant. The standard is to implement the spirit of my country's nuclear safety regulations, actively promote the unification of the standard technical route of mechanical equipment of the nuclear island of pressurized water reactor nuclear power plants, and promote the development of pressurized water reactors. GB/T 16702 is an important part of the relevant standards for the independent design and localization of nuclear island mechanical equipment. The basic and universal standards for design activities of mechanical equipment in the nuclear island of a pressurized water reactor nuclear power plant are planned to consist of eight parts.
1.General. The purpose is to specify the overall requirements and related requirements for the design of mechanical equipment in the nuclear island of a pressurized water reactor nuclear power plant. Appendix for his partial use.
2.Class 1 equipment. The purpose is to specify the materials, design, manufacture, inspection, pressure test and overpressure of Class 1 pressure equipment. Requirements that need to be followed in design such as protection.
1 Scope
GB/T 16702.8-2025 is the Chinese national standard on design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - part 8: low pressure or atmospheric storage tanks, in the field of energy and heat transfer engineering. The /T suffix marks it as a recommended standard: it is not compulsory by itself, but it becomes binding as soon as a contract, a tender or a customer specification calls it up - which in practice is how most foreign buyers meet it. It was issued on 28 February 2025 by the State Administration for Market Regulation; Standardization Administration of China, and has been in force since 28 February 2025. Classification: ICS 27.120.20, CCS F 69. This page is published from the official record of the standard held by the Chinese standards administration: the identification, the dates, the classification and the issuing body are taken from there. The clause text, the tables and the numeric limits are in the document itself, which is delivered complete in English translation.
This document specifies the requirements for materials, design, manufacturing, inspection, etc. of low-pressure or atmospheric pressure storage tanks in the nuclear island mechanical equipment of pressurized water reactor nuclear power plants. The relevant tests were carried out. This document applies to the design of low-pressure or atmospheric pressure storage tanks and their components as specified in Chapter 5 of GB/T 16702.1-2025.
2 Normative references
The contents of the following documents constitute 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 to This document.
GB/T 16702.1-2025 Specification for design of mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part
3 Terms and definitions
The terms and definitions defined in GB/T 16702.1-2025 and the following apply to this document.
3.1 Low pressure storage tank lowpressurestoragetank The interior is isolated from the external atmosphere and is at low pressure, and does not include equipment with pressure-limiting safety devices.
Note. A low-pressure storage tank is a storage tank with a top medium pressure lower than
0.05 MPa.
3.2 Atmospheric storage tank atmospheric storage tank Equipment whose interior is always connected to the external atmospheric environment.
4 Symbols
The following symbols apply to this document.
7 Equipment support
GB/T 17505-2016 General technical requirements for delivery of steel and steel products NB/T.20001-2023 Specification for the manufacture of mechanical equipment for nuclear island of pressurized water reactor nuclear power plant NB/T.20002.6 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part
6.Product welding NB/T.20003.2-2021 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part
2.Ultrasonic testing NB/T.20003.3 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part
3.Radiographic testing NB/T.20003.4 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part
4.Penetrant testing NB/T.20003.5 Nondestructive testing of mechanical equipment in nuclear island of nuclear power plant Part
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 47 pages — is available in the English PDF.
Referenced standards
Normative references
- GB/T 16702.1-2025Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants — Part 1: General principle
- GB/T 16702.3-2025Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 3: Class 2 components
Similar standards
Editions of GB/T 16702.8
| Edition | Title | Revision | Status |
|---|---|---|---|
| GB/T 16702.8-2025 | Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 8: Low pressure or atmospheric storage tanks | current edition | Current |
| GB/T 16702-2019 | Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants | merged into this edition | Superseded |
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Related Standards
GB/T 16702.1-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants — Part 1: General principle
GB/T 16702.3-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 3: Class 2 components
GB/T 16702.2-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 2: Class 1 components
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GB/T 16702.8-2025
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