GB/T 16702.2-2025 English PDFUS$3289.00 · In stock
Delivery: <= 12 days. True-PDF full-copy in English will be manually translated and delivered via email. 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 Status: Valid
Basic dataStandard ID: GB/T 16702.2-2025 (GB/T16702.2-2025)Description (Translated English): Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 2: Class 1 components Sector / Industry: National Standard (Recommended) Classification of Chinese Standard: F69 Classification of International Standard: 27.120.20 Word Count Estimation: 170,142 Date of Issue: 2025-02-28 Date of Implementation: 2025-02-28 Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration 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---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order. GB/T 16702.2-2025 English version. Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 2.Class 1 components ICS 27.120.20 CCSF69 National Standard of the People's Republic of China Partially replaces GB/T 16702-2019 Design specification for mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 2.Class 1 equipment waterreactornuclearpowerplants-Part 2.Class1components Released on 2025-02-28 2025-02-28 Implementation State Administration for Market Regulation The National Standardization Administration issued Table of ContentsPreface III Introduction V 1 Scope 1 2 Normative references 1 3 Terms and definitions 3 4 General 4 4.1 Boundaries of components and accessories of Class 1 equipment and piping 4 4.2 File 8 4.3 Identification 9 5 Materials 10 5.1 Overview 10 5.2 Selection of materials 10 5.3 Intergranular corrosion susceptibility 16 5.4 Cobalt content requirements 17 6 Design17 6.1 Design rules 17 6.2 General principles for equipment performance analysis 22 6.3 General design of containers 48 6.4 Pump Design 63 6.5 General design of valves 65 6.6 Pipeline Design 98 7 Manufacturing and Inspection 144 7.1 Overview 144 7.2 Preliminary documentation and requirements for manufacturing and inspection 145 7.3 Manufacturing Process 146 7.4 Welding related technical requirements 146 8 Pressure testing of Class 1 equipment 149 8.1 General Principles149 8.2 General requirements for water pressure testing 149 8.3 Special test requirements for valves 153 9 Overpressure protection 153 9.1 General Principles153 9.2 Overpressure Analysis Report 157 9.3 Displacement Requirements 158 9.4 Set pressure of direct pressure limiting device 158 9.5 Technical requirements for the design and operation of pressure relief valves 159 9.6 Non-reclosing pressure relief devices 163 9.7 Determination of displacement 163ForewordThis 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 2 of GB/T 16702 "Design Specification for Mechanical Equipment of Nuclear Island in Pressurized Water Reactor Nuclear Power Plant". The following parts are published. --- Part 1.General; --- Part 2.Class 1 equipment; --- Part 3.Level 2 equipment; --- Part 4.Level 3 equipment; --- Part 5.Small equipment; --- Part 6.Reactor internals; --- Part 7.Equipment support; --- Part 8.Low-pressure or atmospheric pressure storage tanks. This document replaces Chapter 5 Level 1 Equipment of GB/T 16702-2019 "Design Specifications for Mechanical Equipment of Nuclear Island in Pressurized Water Reactor Nuclear Power Plants" and Compared with Chapter 5 in GB/T 16702-2019, in addition to structural adjustments and editorial changes, the main technical changes are as follows. --- Added the boundaries of components and accessories of Level 1 equipment and pipelines (see 4.1); --- Changed the material standard number; added 1 level of passive residual heat removal heat exchanger, core water tank, main pump external heat exchanger, etc. Equipment and material selection (see Table 1, Table 2 of the.2019 edition); --- Changed the description of working condition classification (see 6.1.2, 5.3.1.2 of the.2019 edition); --- Added B-level criteria and T-level criteria (see 6.1.4); --- Added some typical stress classifications (see 6.2.3.1.7); --- Changed the stress limits under some working conditions (see 6.2.3, 5.3.2.3 of the.2019 edition); --- Added design principles for geometric and load discontinuity areas [see 6.3.4.2c)]; --- Increased maintainability (see 6.3.4.3); --- Added the design of pressure relief valve (see 6.5.7); --- Changed Table 7 and added the last two columns of materials and their corresponding data (see Table 7, Table 7 of the.2019 edition); --- Changed the requirements for copper and phosphorus content in the weld metal of the high intensity irradiation zone in the welding procedure qualification of low alloy steel butt welds [see 7.2.3.1a), 5.4.2.3.1a) of the.2019 edition]; --- Changed the acceptance requirements for the metal impact toughness test of the heat affected zone of the reactor pressure vessel [see 7.2.3.1b),.2019 edition 5.4.2.3.1b)]; --- Changed the recommended minimum preheating temperature for low alloy steel welding (see 7.4.4, 5.4.4.4 of the.2019 edition); --- Changed the test pressure requirements for single containers (see 8.2.2.1, 5.5.2.2.1 of the.2019 edition); --- Added pressure test requirements for multi-chamber containers (see 8.2.2.1); --- Changed the test pressure requirements for components (see 8.2.2.6, 5.5.2.2.6 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, Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., China Nuclear Power Engineering 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. Wang Xuxin, Tang Chuanbao, Sun Yingxue, Li Donghui, Yang Licai, Qian Sheng, Liu Runfa, Zhang Yaochun, Deng Xiaoyun, Yang Zhihai, Gao Yongjian, Zuo Shuchun, Liu Pan, Zhou Quan, Fu Xiaolong, Yin Qiwei, Huang Zongren, Mei Le, Wang Qingtian, Tan Xin, Li Changxiang, Su Shu, Tian Jun, Zhao Yu, Huang Min, Lü Yongbo, Qiu Yang, Ma Shuli, Qiu Tian, Zhou Gaobin, Jiang Hong, Wang Yan, Kang Zhibin, Liu Xianghong, Liu Hongbin, Yang Chuansheng, Huang Bingyan, Tom Chenhang, Zheng Liangang, He Jinsong, Feng Zhipeng, Liu Wenjin, Zeng Zhongxiu, Li Hongying, Wei Wei, Han Zheng, Yang Jingrui, Wang Bingxi, Guan Jialun, He Yinbiao, Lin Shaoxuan, Zhang Zhichao, Zhang Xing, Bai Yongjun, Gu Chunhui, Tao Hongxin, Chen Hongsheng, Zhang Junbao, Wang Yongdong, Liu Gang, Chen Xingwen, Wang Hongchang, Ni Yiyu, Wang Zhenfeng, Wang Yanping, Guo Lifeng, Lu Xiaohui, Kong Xiaofei, Tang Hui, Li Hailong, Gao Chen, Zhou Zhou, Su Xihui, Wu Feifei, and Deng Ruiyuan. 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;IntroductionGB/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. --- Part 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. --- Part 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. --- Part 3.Class 2 equipment. The purpose is to specify the materials, design, manufacture, inspection, pressure test and overpressure of Class 2 pressure equipment. Requirements that need to be followed in design such as protection. --- Part 4.Class 3 equipment. The purpose is to specify the materials, design, manufacture, inspection, pressure test and overpressure of Class 3 pressure equipment. Requirements that need to be followed in design such as protection. --- Part 5.Small equipment. The purpose is to specify the materials, design, manufacture, inspection, hydraulic test and pump of small pressure equipment. Requirements that need to be followed in the design, such as identification and acceptance testing. --- Part 6.In-core components. The purpose is to specify the materials, design, manufacturing, inspection and other design requirements of in-core components. Require. --- Part 7.Equipment Support. The purpose is to specify the requirements to be followed in the design of mechanical equipment supports in the nuclear island of a pressurized water reactor nuclear power plant. Require. --- Part 8.Low-pressure or atmospheric pressure storage tanks. The purpose is to specify the materials, design, manufacture, inspection and hydraulic test of low-pressure or atmospheric pressure storage tanks. Requirements that need to be followed in design, such as verification. GB/T 16702 (all parts) together with NB/T.20001~NB/T.20009 series of standards constitute the pressurized water reactor nuclear power plant applicable to my country. The technical standard system for the design and manufacture of nuclear island mechanical equipment in power plants. This standard system is based on independent nuclear power engineering experience and incorporates nuclear island mechanical equipment The standard technical route unifies the research results, conforms to the requirements of my country's nuclear power regulatory system and industrial foundation, and is the standard and guide for my country's pressurized water reactor nuclear power plants. It is an important basis for the design and manufacturing of nuclear island mechanical equipment and other related activities. This document focuses on the design principles of Class 1 pressure equipment, adds design requirements for special components and structures, and updates material standards. The number improves the requirements that need to be followed in the design of materials, design, manufacturing, inspection, pressure testing and overpressure protection of Class 1 pressure equipment. This document is used in conjunction with GB/T 16702.1-2025. Design specification for mechanical equipment of nuclear island of pressurized water reactor nuclear power plant Part 2.Class 1 equipment1 ScopeThis document specifies the materials, design, manufacturing, inspection and overpressure protection of Class 1 pressure equipment in the nuclear island mechanical equipment of a pressurized water reactor nuclear power plant. Requirements and corresponding tests are described. This document applies to the design of Class 1 pressure equipment and its components as specified in Chapter 5 of GB/T 16702.1-2025.2 Normative referencesThe 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 to This document. GB/T 16702.1-2025 Specification for design of mechanical equipment for pressurized water reactor nuclear island Part 1.General GB/T 16702.3-2025 Specification for design of mechanical equipment for pressurized water reactor nuclear island Part 3.Level 2 equipment GB/T 16702.6-2025 Specification for design of mechanical equipment for pressurized water reactor nuclear island Part 6.Reactor internals GB/T 16702.7-2025 Specification for design of mechanical equipment for pressurized water reactor nuclear island Part 7.Equipment support parts NB/T.20001 Specification for the manufacture of mechanical equipment for nuclear island of pressurized water reactor nuclear power plant NB/T.20002.1 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 1.General requirements NB/T.20002.2 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 2.Acceptance of welding filler materials NB/T.20002.3 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 3.Welding procedure qualification NB/T.20002.4 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 4.Evaluation of welding filler materials NB/T.20002.5 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 5.Assessment of manufacturing workshop 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.20002.7 Specification for welding of mechanical equipment in nuclear island of pressurized water reactor nuclear power plant Part 7.Wear resistant cladding 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.20004 Physical and chemical testing methods for mechanical equipment materials in nuclear islands of nuclear power plants NB/T.20005.1 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 1.Forgings and rolled products for level 1, 2 and 3 equipment NB/T.20005.5 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 5.Grade 1, 2 and 3 pressure-bearing castings NB/T.20005.6 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 6.Reactor coolant pump motor frame castings NB/T.20005.7 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants Part 7.Steel plates for level 1, 2 and 3 equipment NB/T.20006.1 Alloy steel for pressurized water reactor nuclear power plants Part 1.Manganese-nickel- Molybdenum alloy steel forgings NB/T.20006.3 Alloy steels for pressurized water reactor nuclear power plants Part 3.Manganese-nickel-molybdenum steels for reactor pressure vessel transition sections and flanges Forgings NB/T.20006.4 Alloy steel for pressurized water reactor nuclear power plants Part 4.Manganese-nickel-molybdenum steel forgings for reactor pressure vessel nozzles NB/T.20006.5 Alloy steel for pressurized water reactor nuclear power plants Part 5.Manganese-nickel-molybdenum steel forgings for reactor pressure vessel heads NB/T.20006.6 Alloy steel for pressurized water reactor nuclear power plants Part 6.Manganese-nickel-molybdenum steel forgings for steam generator tube sheets ......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB/T 16702.2-2025_English be delivered?Answer: Upon your order, we will start to translate GB/T 16702.2-2025_English as soon as possible, and keep you informed of the progress. The lead time is typically 8 ~ 12 working days. The lengthier the document the longer the lead time.Question 2: Can I share the purchased PDF of GB/T 16702.2-2025_English with my colleagues?Answer: Yes. The purchased PDF of GB/T 16702.2-2025_English will be deemed to be sold to your employer/organization who actually pays for it, including your colleagues and your employer's intranet.Question 3: Does the price include tax/VAT?Answer: Yes. Our tax invoice, downloaded/delivered in 9 seconds, includes all tax/VAT and complies with 100+ countries' tax regulations (tax exempted in 100+ countries) -- See Avoidance of Double Taxation Agreements (DTAs): List of DTAs signed between Singapore and 100+ countriesQuestion 4: Do you accept my currency other than USD?Answer: Yes. If you need your currency to be printed on the invoice, please write an email to Sales@ChineseStandard.net. In 2 working-hours, we will create a special link for you to pay in any currencies. Otherwise, follow the normal steps: Add to Cart -- Checkout -- Select your currency to pay. |
