GB 6249-1986
Replaced
GB/T 16702-2019
Active
National standards
GB/T 16702-2019 Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
GB/T 16702-2019 Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
Price:
$ 503
Basic Information
Standard Code:
GB/T 16702-2019
Standard Type:
National standards
Standard Status:
Active
is_force_gb:
no
CCS Name:
Nuclear reactors and nuclear island equipment in nuclear power plants
ICS Name:
Nuclear power stations, safety
Publish Date:
2019-12-31
Implement Date:
2020-07-01
Pages:
722 pages
Scope
This standard specifies the design rules for nuclear island mechanical equipment of pressurized water reactor nuclear power plants, including Class 1 equipment, Class 2 equipment, Class 3 equipment, small equipment, reactor internals, equipment supports, and low-pressure or atmospheric pressure storage tanks.
This standard is applicable to the design of nuclear island mechanical equipment of pressurized water reactor nuclear power plants.
Development Information
Replace the following standards
Superseded by the following standards
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
Referenced Standards
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 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants—Part 22: Seamless Steel Tubes of Martensitic Stainless Steel for Reactor Control Rod Drive Mechanisms
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 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants - Part 24: Pressure-Resistant Castings of Austenitic-Ferritic Stainless Steel for Reactor Coolant Pump Impellers
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 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants - Part 27: Austenitic-Ferritic Stainless Steel Cast Elbows and Beveled Pipe Nozzles for Reactor Coolant Pipelines
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 Other materials for pressurized water reactor nuclear power plants - Part 2: Manganese-molybdenum-vanadium alloy steel castings for steam generators, reactor coolant pumps, and main steam pipeline supports
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 Other materials for pressurized water reactor nuclear power plants - Part 11: Forged and rolled rods for pins, tie rods, and support bolts of grades S1 and S2
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
Related Standards
GB/T 12726.1-1991
Replaced
GB/T 12726.1-1991 Radiation monitoring equipment for accident and post-accident conditions in nuclear power plants—Part 1:General requirements
GB/T 13178-1991
Replaced
GB/T 13178-1991 Partially depleted gold silicon surface barrier detectors
GB/T 13180-1991
Replaced
GB/T 13180-1991 G-M counter tubes for detecting γ radiation
GB/T 13182-1991
Replaced
GB/T 13182-1991 Scintillation detectors of sodium iodide (thallium)
GB/T 12726.2-1991
Replaced