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 16702.1-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 1:General principle 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 GB/T 16702.4-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 4:Class 3 components GB/T 16702.5-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 5:Small components GB/T 16702.6-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 6:Reactor vessel internals GB/T 16702.7-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 7:Supports 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

GB/T 16702-2019 Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants

GB/T 150.3-2024 Pressure vessels—Part 3:Design GB 151-1999 Tubular heat exchangers GB/T 151-2014 Heat exchangers GB/T 151-2026 Heat exchangers GB/Z 151-2026 Fire prevention measures on converters for high-voltage direct current(HVDC)systems,static var compensators(SVC)and flexible AC transmission systems(FACTS)and their valve halls 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 16702.2-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 2:Class 1 components GB/T 16702.7-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 7:Supports NB/T 20001-2023 Nuclear Island mechanical equipment manufacturing specifications for pressurized water reactor nuclear power plants NB/T 20002.1-2021 Pressurized Water Reactor Nuclear Power Plant Nuclear Island Machinery Welding Specification Part 1: General Requirements NB/T 20002.5-2013 Nuclear Island Machinery and Equipment Welding Specification Part 5: Manufacturing Plant Evaluation for Pressurized Water Reactor Nuclear Power Plants NB/T 20002.6-2021 Pressurized Water Reactor Nuclear Power Plant Nuclear Island Machinery Welding Specification Part 6: Product Welding Standards for Welding Operations NB/T 20002.7-2013 Pressurized water reactor nuclear power plant nuclear island mechanical equipment welding specifications Part 7: Wear-resistant surface welds NB/T 20003.1-2021 Nuclear power plant equipment inspection for non-destructive testing - Part 1: General requirements NB/T 20003.1-2010 Nuclear plant equipment inspection for defects without damaging the equipment in the nuclear island - Part 1: General requirements NB/T 20003.2-2021 Nuclear Power Plant Mechanical Equipment Nondestructive Testing Part 2: Ultrasonic Testing for Nuclear Island (NB/T 20003.2-2021) NB/T 20003.2-2010 Nuclear power plant equipment and machinery - Non-destructive testing - Part 2: Ultrasonic testing NB/T 20003.3-2021 Nuclear power plant equipment machinery without damage testing - Part 3: Radiographic testing NB/T 20003.3-2010 Nuclear equipment for nuclear island - Non-destructive testing - Part 3: Radiographic testing NB/T 20003.4-2021 Nuclear power plant equipment inspection for non-destructive testing - Part 4: Penetration testing NB/T 20003.4-2010 Non-destructive testing for mechanical components in nuclear island of nuclear power plants-Part 4:Penetrant testing NB/T 20003.5-2021 Nuclear plant machinery equipment non-destructive testing - Part 5: Magnetic particle testing NB/T 20003.5-2010 Nuclear equipment inspection of the nuclear island machinery: Part 5: Magnetic particle inspection. (Translation of Chinese text only) NB/T 20003.6-2021 Nuclear Island mechanical equipment non-destructive testing - Part 6: Eddy current testing NB/T 20003.6-2010 Non-destructive testing for mechanical components in nuclear island of nuclear power plants-Part 6:Eddy current testing of tubular products NB/T 20003.7-2021 Nuclear Island machinery equipment non-destructive testing - Part 7: Visual inspection (English translation only) NB/T 20003.7-2010 Nuclear Island Machinery and Equipment Nondestructive Testing Part 7: Visual Inspection (English) NB/T 20003.8-2021 Nuclear power plant equipment inspection for non-destructive testing Part 8: Leakage testing NB/T 20003.8-2010 Nuclear facilities machinery and equipment for non-destructive testing - Part 8: Leakage testing for nuclear island equipment NB/T 20004-2014 Methods for physical and chemical examination of mechanical equipment materials in nuclear power plant nuclear island NB/T 20004-2011 Nuclear power plant mechanical equipment material physical and chemical inspection methods for nuclear island NB/T 20005.1-2010 Pressurized water reactor nuclear power plant carbon steel and low alloy steel for grades 1, 2, and 3 forged parts NB/T 20005.1-2024 Pressurized water reactor nuclear power plant equipment: Carbon steel and low alloy steel for use in grades 1, 2, and 3, including for forged and rolled components NB/T 20005.5-2013 Pressurized water reactor nuclear power plant carbon steel and low alloy steel - Part 5: Class 1, 2, and 3 pressure castings NB/T 20005.7-2017 NB/T 20005.7-2017 Pressurized Water Reactor NPP Steel and Low Alloy Steel - Part 7: Grades of steel plates for 1, 2, and 3 levels NB/T 20005.7-2010 Pressurized water reactor nuclear power plant carbon steel and low alloy steel - Part 7: Grades of steel plate for Class 1, 2, and 3 NB/T 20005.7-2024 Pressurized water nuclear power plant - Carbon steel and low alloy steel for equipment - Part 7: Steel plates for Class 1, 2, and 3 equipment NB/T 20005.9-2017 Pressurized water nuclear power plant carbon steel and low alloy steel - Part 9: Seamless steel pipes for Classes 2 and 3 NB/T 20005.9-2010 Pressurized water reactor nuclear power plant - Carbon steel and low alloy steel for grades 1, 2, and 3 seamless pipes NB/T 20005.9-2024 Pressurized water nuclear power plant carbon steel and low alloy steel - Part 9: Seamless steel pipes for Class 2 and Class 3 equipment NB/T 20005.10-2013 Pressurized water nuclear power plant carbon steel and low alloy steel - Part 10: Grade 2 and 3 welded steel pipes with filler metal NB/T 20005.10-2024 NB/T 20005.10-2024 Pressurized Water Nuclear Power Plant - Carbon Steel and Low Alloy Steel for Pressure Pipe - Part 10: Welded Steel Tubes for Class 2 and Class 3 Equipment, Filled Metal Welding Method NB/T 20005.12-2017 Pressurized water nuclear power plant - Carbon steel and low alloy steel for steam systems, main feedwater flow control systems, auxiliary feedwater systems, and steam-turbine bypass systems - Seamless steel pipes and tubing for pressure vessel components used in the main steam system, main feedwater flow control systems, auxiliary feedwater systems, and steam-turbine bypass system of a pressurized water nuclear power plant - Part 12: Seamless steel pipes and tubes for the turbine bypass system. (Note: The text in parentheses is provided for reference only.) NB/T 20005.12-2010 Pressurized water nuclear power plant - Carbon steel and low alloy steel for steam systems, main feedwater flow control systems, auxiliary feedwater systems, and steam turbine bypass systems - Seamless steel pipes and tubes - Part 12 NB/T 20005.13-2012 Pressurized water nuclear power plant carbon steel and low alloy steel - Part 13: Seamless cold-drawn tube for heat exchanger heat transfer - Grades 2 and 3 NB/T 20005.14-2012 Pressurized water reactor nuclear power plant - Carbon steel and low alloy steel - Part 14: Grade 2 and 3 welded seamless piping fittings NB/T 20005.15-2013 NB/T 20005.16-2012 Pressurized water nuclear power plant - Carbon steel and low alloy steel for main steam system - Part 16: Bends used in main steam system NB/T 20005.16-2024 Pressurized water nuclear power plant - Carbon steel and low alloy steel for pressure vessel components - Part 16: Bends for main steam pipes NB/T 20007.1-2021 Pressurized water reactor nuclear power plant grade stainless steel forged parts of austenitic stainless steel grades 1, 2, and 3 NB/T 20009.26-2014 Welding Materials for Pressurized Water Reactor Nuclear Power Plants - Part 26: Carbon Steel Gas Shielding Electro-Arc Welding Wire for Safety-Grade Equipment NB/T 20009.27-2017 Pressurized water nuclear power plant welding materials - Part 27: Stainless steel welding wire for safety-level equipment NB/T 20009.28-2015 Welding Materials for Pressurized Water Reactor Nuclear Power Plants - Part 28: Nickel-based alloys for safety-level equipment welding wires NB/T 20009.29-2014 NB/T 20009.29-2014 Welding Materials for Nuclear Power Plants Part 29: Carbon Steel Welding Wire and Welding Solder for Under-Scaffold Welding of Safety-Grade Equipment NB/T 20009.30-2017 Pressurized water nuclear power plant welding materials - Part 30: Low alloy steel welding wire and welding flux for safety class 1 equipment arc welding NB/T 20009.31-2017 Pressurized water nuclear power plant welding materials - Part 31: Safety-grade equipment stainless steel welder's tape and welding flux for surface welds NB/T 20009.32-2018 Welding Materials for Pressurized Water Reactor Nuclear Power Plants - Part 32: Gas-shielding welding wire for low alloy steel NB/T 20009.33-2015 Pressurized water nuclear power plant welding materials - Part 33: Stainless steel welding wire and flux for in-service arc welding of safety-related equipment NB/T 20009.34-2017 Pressurized water nuclear power plant welding materials - Part 34: Nickel-based alloys for safety-level equipment welding strips and fluxes for surface welds NB/T 20009.35-2014 NB/T 20009.36-2018 Welded materials for pressurized water reactor nuclear power plants - Part 36: Gas shielded welding wire for steel containment vessel NB/T 20010.9-2010 PWR nuclear power plant valve-Part 9:Final examination and test in manufactory NB/T 20036.6-2011 Nuclear Power Plant Mechanical Equipment Inspection Part 6: Valve Component Inspection ASME B16.5-2017 ASME B16.9 ASME B16.11 ASME B16.25 ASME B16.47 ASME B36.10M ASME B36.19M