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Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant
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GB/T 42143-2022
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Basic data | Standard ID | GB/T 42143-2022 (GB/T42143-2022) | | Description (Translated English) | Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 101,166 | | Date of Issue | 2022-12-30 | | Date of Implementation | 2023-07-01 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 42143-2022: Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant
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ICS 27.120.20
CCSF69
National Standards of People's Republic of China
Code for design and construction of steel containment for pressurized water reactor nuclear power plants
Posted on 2022-12-30
2023-07-01 implementation
State Administration for Market Regulation
Released by the National Standardization Management Committee
table of contents
Preface III
1 Scope 1
2 Normative references 1
3 Terms, Definitions and Symbols 2
3.1 Terms and Definitions 2
3.2 Symbol 3
4 General principles and requirements 4
4.1 General 4
4.2 The jurisdictional boundaries of this document5
5 material 10
5.1 General 10
5.2 General requirements for materials 12
5.3 Specimens and specimens of ferritic steel 13
5.4 Fracture toughness requirements of materials 16
5.5 Welding consumables 21
5.6 Inspection and repair of pressure-bearing materials 21
6 designs 25
6.1 Design principles 25
6.2 Formula Design 27
6.3 Analytical design 33
6.4 Openings and opening reinforcement 43
6.5 Welded connection design 47
6.6 Stress limitation of bolts 52
6.7 Special requirements 53
6.8 Electrical and mechanical penetrations 53
7 Fabrication and installation 53
7.1 General 53
7.2 Forming, fitting and centering 54
7.3 Welding and qualification 69
7.4 Mechanical joints and penetrations 69
8 detection 71
9 trials 71
9.1 General 71
9.2 Structural integrity test 72
9.3 Leakage test 72
10 Overpressure Protection 72
10.1 General 72
10.2 External pressure protection 73
Appendix A (Normative) Material Properties 74
Appendix B (Informative) According to TNDT, the minimum allowable service temperature of the metal of steel containment components is 80
Appendix C (Normative) Charts for External Pressure Calculation 81
Appendix D (Normative) Design Fatigue Curve 91
References 96
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.
Please note that some contents of this document may refer to patents. The issuing agency of this document assumes no responsibility for identifying patents.
This document is proposed and managed by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).
This document is drafted by. Shanghai Nuclear Engineering Research and Design Institute Co., Ltd.
The main drafters of this document. Ge Honghui, Chen Laiyun, Liu Shenghua, Huang Xiaolin, Zhang Junbao, Wang Yongdong.
Code for design and construction of steel containment for pressurized water reactor nuclear power plants
1 Scope
This document specifies the materials, design, manufacture and installation, testing, testing and overpressure protection of steel containment for PWR nuclear power plants.
This document is applicable to the design and construction of the steel containment of PWR nuclear power plants, and the same type of containment for other reactor-type nuclear power plants can be implemented as a reference.
2 Normative references
The contents of the following documents constitute the essential provisions of this document through normative references in the text. Among them, dated references
For documents, only the version corresponding to the date is applicable to this document; for undated reference documents, the latest version (including all amendments) is applicable to
this document.
GB/T 229 Charpy pendulum impact test method for metallic materials
GB/T 6803 drop weight test method for non-plastic transition temperature of ferritic steel
GB/T 16702-2019 Code for Design of Nuclear Island Mechanical Equipment in Pressurized Water Reactor Nuclear Power Plant
GB/T 17569 Classification of Pressurized Water Reactor Nuclear Power Plant Items
NB/T.20002.1 Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant Part 1.General requirements
NB/T.20002.2 Code for Welding of Nuclear Island Mechanical Equipment in Pressurized Water Reactor Nuclear Power Plant Part 2.Acceptance of Welding Filling Materials
NB/T.20002.3 Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant Part 3.Welding procedure qualification
NB/T.20002.6-2021 Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant Part 6.Product welding
NB/T.20003.7 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants Part 7.Visual testing
NB/T.20003.8 Non-destructive testing of nuclear island machinery and equipment in nuclear power plants - Part 8.Leak detection
NB/T.20005.31 Carbon steel and low alloy steel for pressurized water reactor nuclear power plant Part 31.15Mn forgings for containment
NB/T.20005.32 Carbon steel and low alloy steel for pressurized water reactor nuclear power plant Part 32.15MnHR steel plate for containment
NB/T.20005.33 Carbon steel and low alloy steel for pressurized water reactor nuclear power plant Part 33.15Mn steel pipe for containment
NB/T.20005.38 Carbon steel and low alloy steel for pressurized water reactor nuclear power plant Part 38.15MnHR for containment mechanical penetrations
Welded steel pipe
NB/T.20005.39 Carbon and low alloy steels for pressurized water reactor nuclear power plants Part 39.15Mn forgings for containment mechanical penetrations
NB/T.20006.31 Alloy steel for pressurized water reactor nuclear power plant Part 31.10MnNiMoHR steel plate for containment
NB/T.20006.32 Alloy steels for pressurized water reactor nuclear power plants Part 32.15Cr1Mo forgings for containment mechanical penetrations
NB/T.20007.31 Stainless steel for pressurized water reactor nuclear power plant Part 31.022Cr19Ni10 stainless steel forgings for containment
NB/T.20007.32 Stainless Steel for Pressurized Water Reactor Nuclear Power Plant Part 32.022Cr19Ni10 Stainless Steel Seamless Tube for Containment
NB/T.20007.35 Stainless steel for pressurized water reactor nuclear power plant Part 35.06Cr18Ni11Ti stainless steel for containment mechanical penetrations
steel plate
NB/T.20008.12-2010 Other materials for pressurized water reactor nuclear power plants Part 12.Forgings, bolts and nuts for Class 1, 2, and 3 equipment
rolling rod
NB/T.20009.35-2014 Welding consumables for pressurized water reactor nuclear power plants Part 35.Low alloy steel electrodes for steel containment
NB/T.20009.36-2018 Welding consumables for pressurized water reactor nuclear power plants Part 36.Gas shielded welding wire for steel containment
NB/T.20018 Containment Leakage Test of Pressurized Water Reactor Nuclear Power Plant
NB/T 20328.2-2015 Another specification for non-destructive testing of nuclear island machinery and equipment in nuclear power plants Part 2.Ultrasonic testing
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