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

GB/T 16702-1996 Design rules for mechanical components of PWR nuclear islands

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 16702.6-2025 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 16702.4-2025 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 16702.1-2025 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 16702.3-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 3:Class 2 components

NB/T 20007.16-2021 Pressurized water reactor nuclear power plant stainless steel - Part 16: Martensitic stainless steel forged parts of grades 2 and 3 NB/T 20007.16-2012 Pressurized water reactor nuclear power plant stainless steel - Part 16: Martensitic stainless steel forged parts of grades 2 and 3 NB/T 20007.17-2021 NB/T 20007.17-2021 Pressurized Water Reactor (PPR) nuclear power plant stainless steel - Part 17: Martensitic stainless steel for clamping springs of internals support components NB/T 20007.17-2012 Pressurized water reactor nuclear power plant stainless steel - Part 17: Martensitic stainless steel for clamping springs used in the internals of the reactor vessel NB/T 20007.18-2012 Pressurized water reactor nuclear power plant - Stainless steel for grade 2 and 3 auxiliary pump drive shaft - Part 18: Forgings and rolled sheets of martensitic stainless steel for use in drive shafts NB/T 20007.19-2021 Pressurized water reactor nuclear power plant stainless steel, Part 19: Pressurized castings of martensitic stainless steel for grades 1, 2, and 3 NB/T 20007.19-2013 Pressurized water reactor nuclear power plant stainless steel - Part 19: Pressurized castings of martensitic stainless steels for classes 1, 2, and 3 use NB/T 20007.20-2013 Pressurized water reactor nuclear power plant stainless steel for Class 20: Pressurized casting components for pumps, martensitic stainless steel A, B, C for non-pressure applications NB/T 20007.21-2012 Pressurized water reactor nuclear power plant stainless steel for steam generator support tube support: Martensitic stainless steel plate for steam generator heat transfer tube support NB/T 20007.22-2012 NB/T 20007.23-2021 Pressurized water reactor nuclear power plant stainless steel - Part 23: Pressurized castings of Austenitic-Ferritic stainless steel grades 1, 2, and 3 for pressure vessel components NB/T 20007.23-2013 NB/T 20007.23-2013 Pressurized Water Reactor Nuclear Power Plant Stainless Steel - Part 23: Pressure Casting Components of Austenitic-Ferritic Stainless Steel for Classes 1, 2, and 3 in Pressurized Water Reactor Nuclear Power Plants NB/T 20007.24-2013 NB/T 20007.25-2021 Pressurized water reactor nuclear power plant stainless steel for piping and equipment Part 25: Non-pressure cast inner parts of austenitic-ferritic stainless steel grades A, B, and C for use in pumps NB/T 20007.25-2013 Pressurized water reactor nuclear power plant stainless steel - Part 25: Non-molybdenum chromium-nickel austenitic-ferritic stainless steel for pump non-fused cast internal components of classes A, B, and C. (English translation) NB/T 20007.26-2012 Pressurized water nuclear power plant stainless steel - Part 26: Austenitic-ferritic stainless steel for centrifugally cast pipes for reactor coolant piping NB/T 20007.27-2013 NB/T 20007.33-2015 Pressurized water reactor nuclear power plant - Stainless steel for reactor coolant piping - Part 33: 015Cr17Ni12Mo2N stainless steel ductile pipes for reactor coolant piping NB/T 20007.36-2015 Pressurized water reactor nuclear power plant stainless steel - Part 36: Austenitic stainless steel for forged bars used in control rod drive mechanism pressure-bearing components NB/T 20007.39-2015 Pressurized water reactor nuclear power plant stainless steel - Part 39: Martensitic stainless steel bars for control rod drive mechanism drives NB/T 20007.40-2015 NB/T 20007.40-2015 Pressurized Water Reactor Nuclear Power Plant - Stainless Steel for Internal Components - Part 40: Austenitic Stainless Steel Forgings for Internal Components NB/T 20007.41-2015 Pressurized water nuclear power plant stainless steel for nuclear reactor internal components Part 41: Austenitic stainless steel seamless steel pipes for reactor internals NB/T 20007.43-2016 Pressurized water nuclear power plant stainless steel - Part 43: 022Cr17Ni12Mo2N austenitic stainless steel for the connection flange of reactor coolant piping forged parts used in pressure water reactor coolant pipeline NB/T 20007.44-2016 Pressurized water nuclear power plant stainless steel - Part 44: 015Cr17Ni12Mo2N austenitic stainless steel tube for reactor coolant fluctuation NB/T 20007.45-2017 Pressurized water reactor nuclear power plant - Stainless steel for clamping springs and washers used in the assembly of pressure retaining components: 04Cr13Ni5Mo martensitic stainless steel forged components. Note: This is the English translation of a Chinese document NB/T 20007.46-2017 Pressurized water reactor nuclear power plant - Stainless steel for steam generators - Part 46: 06Cr13Al stainless steel plate for steam generators NB/T 20007.47-2017 Pressurized water reactor nuclear power plant stainless steel - Part 47: 06Cr13Al stainless steel flange steel for steam generators NB/T 20008.1-2012 Pressurized Water Reactor Nuclear Power Plant - Other Materials - Part 1: Alloy Steel Forgings for Reactor Coolant System Support Components NB/T 20008.2-2010 NB/T 20008.3-2012 Other Materials for Pressurized Water Nuclear Power Plant - Part 3: Copper-aluminum alloy castings for Class 3 auxiliary system pumps and valves NB/T 20008.4-2012 Pressurized Water Reactor NPP Material Handbook: Other Materials for Pressurized Water Reactors - Part 4: Rolled and forged nickel-chromium-iron alloys for Classes 1, 2, and 3 NB/T 20008.4-2024 NB/T 20008.4-2024 Other Materials for Pressurized Water Nuclear Power Plant, Part 4: Nickel-chromium-iron alloy forged and rolled parts for Class 1, 2, 3 equipment NB/T 20008.5-2012 Pressurized water reactor nuclear power plant - Other materials for use in the 5th Part: Hot-rolled nickel-chromium-iron alloy plates for Class 1 and 2 purposes NB/T 20008.6-2012 NB/T 20008.6-2012 Other Materials for Pressurized Water Nuclear Power Plant - Part 6: Nickel-chromium-iron alloy hot rolled plate NB/T 20008.6-2024 Other Materials for Pressurized Water Nuclear Power Plant - Part 6: Nickel-base Corrosion Resistant Alloy Sheet NB/T 20008.7-2021 Other Materials for Pressurized Water Nuclear Power Plant - Part 7: Nickel-chromium-iron Alloy Seamless Tubes for Steam Generator Heat Transfer Tubes NB/T 20008.7-2013 NB/T 20008.7-2013 Other Materials for Pressurized Water Nuclear Power Plant - Part 7: Nickel-chromium-iron alloys seamless tube for steam generator heat transfer tube NB/T 20008.8-2021 Other Materials for Pressurized Water Reactor Nuclear Power Plants - Part 8: Heat-Extruded Tubes of Nickel-Chromium-Iron Alloy NB/T 20008.8-2012 NB/T 20008.8-2012 Other Materials for Pressurized Water Nuclear Power Plant - Part 8: Nickel-chromium-iron alloy hot extruded tube for nuclear power plant NB/T 20008.8-2024 Other Materials for Pressurized Water Nuclear Power Plant - Part 8: Nickel-base Corrosion Resistant Alloy Tubes NB/T 20008.9-2012 The use of other materials for pressurized water reactor nuclear power plants - Part 9: Nickel-chromium-iron alloy hot-rolled or hot-extruded rods NB/T 20008.9-2024 Other Materials for Pressurized Water Reactor Nuclear Power Plants - Part 9: Nickel-based Corrosion Resistant Alloy Rods NB/T 20008.10-2012 Pressurized Water Reactor NPP Material for Other Components - Part 10: Nickel-chromium-iron alloy rolled bars for internal component pins and bolted fasteners in the reactor NB/T 20008.10-2024 NB/T 20008.10-2024 Other Materials for Pressurized Water Nuclear Power Plant - Part 10: Nickel-based alloys for internals and control rod drive mechanisms NB/T 20008.11-2013 NB/T 20008.11-2024 Pressurized water reactor nuclear power plant - Other materials used for supporting and connecting parts - Part 11: Rolled and forged bars for support and connection parts NB/T 20008.12-2010 NB/T 20008.12-2010 Other Materials for Pressurized Water Nuclear Power Plant Part 12: Forged and Rolled Bars for Bolts and Screws of Class 1, 2 and 3 Equipment in Pressurized Water Nuclear Power Plant NB/T 20008.13-2013 Other Materials for Pressurized Water Reactor Nuclear Power Plants - Part 13: Bolts, screws, bolts, screws, rods and nuts for Class 1, 2 and 3 applications NB/T 20008.15-2012 The use of other materials in pressurized water nuclear power plants - Part 15: Titanium sheets for Class 3 plate heat exchangers NB/T 20008.17-2012 Other Materials for Pressurized Water Nuclear Power Plant - Part 17: Grades 2 and 3 Non-alloy and Alloy Ductile Iron Components NB/T 20008.24-2015 The other materials used in pressurized water reactor nuclear power plants - Part 24: GH4145 alloy bars for internals of the reactor NB/T 20008.27-2017 Other Materials for Pressurized Water Nuclear Power Plant - Part 27: ZCoCr29W4.5 Castings for Control Rod Drive Mechanism NB/T 20008.28-2017 Other Materials for Pressurized Water Reactor Nuclear Power Plants - Part 28: NS3105 Alloy Forgings for Safety-Grade Equipment (NS3105 Alloy Forgings for Nuclear Power Plant Safety Equipment) NB/T 20008.29-2017 The use of other materials in pressurized water reactor nuclear power plants - Part 29: NS3105 alloy plate and strip for safety-level equipment. English translation: NS3105 alloy plate and strip for safety-level equipment NB/T 20008.30-2017 Other Materials for Pressurized Water Nuclear Power Plant - Part 30: NS3105 Alloy Tubes for Safety-Grade Equipment (for Nuclear Power Plant) NB/T 20008.31-2017 Other Materials for Pressurized Water Nuclear Power Plant - Part 31: NS3105 Alloy Bars for Safety-Critical Equipment (NS3105 alloy used in pressure-resistant equipment for nuclear power plant) NB/T 20008.32-2017 NB/T 20008.32-2017 Other Materials for Pressurized Water Nuclear Power Plant - Part 32: NS3306 Alloy Sheet and Strip for Control Rod Drive Mechanism NB/T 20008.34-2018 Other Materials for Pressurized Water Nuclear Power Plant - Part 34: NS3105 Alloy U-Tube for Steam Generator. (Note: The exact translation may vary depending on the context and usage.) 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