GB/T 42143-2022Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant (English PDF)
压水堆核电厂钢制安全壳设计建造规范
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Issued by
SAMR; SAC
Level / Type
National · Recommended
Issue date
December 30, 2022
Implementation date
July 1, 2023
Scope
GB/T 42143-2022 is the English-translated version of 压水堆核电厂钢制安全壳设计建造规范.
GB/T 42143-2022 is the Chinese standard "Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant".
Its scope clause reads: 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.
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Document preview — GB/T 42143-2022
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 the PRC
Contents
- Preface
- 1 Scope
- 2 Normative references
- 3 Terms, Definitions and Symbols
- 3.1 Terms and Definitions
- 3.2 Symbol
- 4 General principles and requirements
- 4.1 General
- 4.2 The jurisdictional boundaries of this document
- 5 material
- 5.1 General
- 5.2 General requirements for materials
- 5.3 Specimens and specimens of ferritic steel
- 5.4 Fracture toughness requirements of materials
- 5.5 Welding consumables
- 5.6 Inspection and repair of pressure-bearing materials
- 6 designs
- 6.1 Design principles
- 6.2 Formula Design
- 6.3 Analytical design
- 6.4 Openings and opening reinforcement
- 6.5 Welded connection design
- 6.6 Stress limitation of bolts
- 6.7 Special requirements
- 6.8 Electrical and mechanical penetrations
- 7 Fabrication and installation
- 7.1 General
- 7.2 Forming, fitting and centering
- 7.3 Welding and qualification
- 7.4 Mechanical joints and penetrations
- 8 detection
- 9 trials
- 9.1 General
- 9.2 Structural integrity test
- 9.3 Leakage test
- 10 Overpressure Protection
- 10.1 General
- 10.2 External pressure protection
- Appendix A (Normative) Material Properties
- Appendix C (Normative) Charts for External Pressure Calculation
- Appendix D (Normative) Design Fatigue Curve
- References
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 […]
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 96 pages — is available in the English PDF.
Referenced standards
Normative references
- GB/T 229Metallic Materials — Charpy Pendulum Impact Test Method
- GB/T 6803Test method for drop-weight test to determine nil-ductility transition temperature of ferritic steels
- GB/T 16702-2019Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
- GB/T 17569Classification for the items of pressurized water reactor nuclear power plants
- NB/T 20002.1Welding code for mechanical components of PWR nuclear islands - Part 1: General requirements
- NB/T 20002.2Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant - Part 2: Acceptance of welding filler materials
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Related Standards
GB/T 16702-2019 — Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
GB/T 17569-2021 — Classification for the items of pressurized water reactor nuclear power plants
GB/T 229-2020 — Metallic Materials — Charpy Pendulum Impact Test Method
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