GB 6249-1986
Replaced
GB/T 16702.1-2025
Active
National standards
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 16702.1-2025 Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 1:General principle
Basic Information
Standard Code:
GB/T 16702.1-2025
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:
2025-02-28
Implement Date:
2025-02-28
Pages:
376 pages
Scope
This document specifies the general design requirements for the mechanical equipment of the nuclear island in pressurized water reactor nuclear power plants.
This document is applicable to the design of mechanical equipment (pressure-bearing equipment and its supports, reactor internals) in pressurized water reactor nuclear power plants.
Development Information
Same series standard
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
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
Replace the following standards
Referenced Standards
NB/T 20005.6-2013 Pressurized water nuclear power plant - Carbon and low alloy steel for parts - Part 6: Castings for the motor base of the reactor coolant pump
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 20005.8-2012 Pressurized water nuclear power plant - Carbon and low alloy steel for supporting components - Part 8: Steel plates, channel steel, and steel bars for class S1 and S2 support components
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 20005.15-2013
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 20007.1-2010 Pressurized water reactor nuclear power plant specifications for stainless steel, Part 1: High-temperature, ductile grades of austenitic stainless steel forgings in Classes 1, 2, and 3
NB/T 20007.1-2024 Pressurized water reactor nuclear power plant stainless steel for pressure vessel equipment - Part 1: Austenitic stainless steel for forged parts used in Class 1, 2, and 3 equipment
NB/T 20007.3-2021 NB/T 20007.3-2021 Pressurized Water Reactor Nuclear Power Plant - Part 3: Austenitic Stainless Steel Forgings for Core Support Plates and Upper Support Plates
NB/T 20007.3-2012 Pressurized water reactor nuclear power plant stainless steel - Part 3: Nitrogen control austenitic stainless steel for core support members and upper support plates for forged parts
NB/T 20007.4-2012 Pressurized water reactor nuclear power plant stainless steel for reactor coolant pump shafts - Part 4: Nb stabilized austenitic stainless steel forged parts used in reactor coolant pump shafts. (English translation)
NB/T 20007.5-2021 Pressurized water reactor nuclear power plant stainless steel - Part 5: Grade 1, 2, and 3 austenitic stainless steel sheets
NB/T 20007.5-2010 Pressurized water reactor nuclear power plant stainless steel - Part 5: Grade 1, 2, and 3 austenitic stainless steel plates. (English translation only)
NB/T 20007.5-2024 Pressurized water reactor nuclear power plant - Stainless steel for pressure vessel equipment - Part 5: Austenitic stainless steel plates for Class 1, 2, and 3 equipment
NB/T 20007.6-2012 Pressurized water nuclear power plant stainless steel - Part 6: Controlled nitrogen austenitic stainless steel plate for internal components
NB/T 20007.6-2024 Pressurized water nuclear power plant stainless steel for reactor internal components - Part 6: Austenitic stainless steel plates for reactor internals
NB/T 20007.8-2017 Pressurized water reactor nuclear power plant stainless steel - Part 8: Seamless steel pipes for austenitic stainless steels grades 1, 2, and 3
NB/T 20007.8-2010 Pressurized water reactor nuclear power plant stainless steel - Part 8: Seamless stainless steel tube for Classes 1, 2, and 3 austenitic stainless steel
NB/T 20007.8-2024 Pressurized water nuclear power plant stainless steel - 8th edition: Seamless stainless steel tube for austenitic stainless steel used in Class 1, 2, and 3 equipment of nuclear power plant
NB/T 20007.9-2011 Pressurized water nuclear power plant stainless steel - Part 9: Seamless welded tube fittings for austenitic stainless steels grades 1, 2, and 3
NB/T 20007.10-2013 Pressurized water nuclear power plant stainless steel - Part 10: Cold-rolled and cold-drawn austenitic stainless steel seamless steel pipes for heat exchanger tubing of grades 2 and 3
NB/T 20007.10-2024 NB/T 20007.10-2024 Pressurized Water Reactor Nuclear Power Plant - Stainless Steel for Heat Exchanger Applications Part 10: Seamless Austenitic Stainless Steel Tubes for Class 1, 2, and 3 Heat Exchangers
NB/T 20007.11-2013 Pressurized water reactor nuclear power plant - Stainless steel for Class 1, 2 and 3 stainless austenitic steel tube for welding - Part 11: Paste-filled, welded stainless austenitic steel tube of grade 1, 2, and 3
NB/T 20007.12-2013 NB/T 20007.12-2013 Stainless steel for pressurized water reactor nuclear power plants - Part 12: Grade 1, 2 and 3 austenitic welded stainless steel pipe fittings of weld metal filler material
NB/T 20007.13-2012 Pressurized water nuclear power plant stainless steel - Part 13: Controlled nitrogen austenitic stainless steel for reactor coolant piping, forged and bent tube
NB/T 20007.14-2021 Pressurized water reactor nuclear power plant stainless steel - Part 14: forged and rolled bars of austenitic stainless steels grades 1, 2, and 3
NB/T 20007.14-2010 Stainless steel for pressurized water reactor nuclear power plants-Part 14:Class 1,2,3 austenitic stainless steel forged or rolled bars
NB/T 20007.14-2024 Pressurized water nuclear power plant stainless steel for pressure vessel no. 14: Stainless steel rods and profiles for austenitic stainless steel equipment in classes 1, 2, and 3 for use in pressurized water nuclear power plant vessels
NB/T 20007.15-2012
NB/T 20007.15-2024 NB/T 20007.15-2024 Pressurized Water Reactor Nuclear Power Plant - Stainless Steel for Internal Components and Core Measurement Sealing Components Fasteners - Cold Work Hardening Austenitic Stainless Steel Bars
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 20007.19-2021 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 20007.21-2012 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 20007.23-2021 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 20007.26-2012 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 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
HAD003/08
HAF 003-1991 Nuclear power plant quality assurance safety regulations
HAF 601-2008 Regulations on the Design, Manufacture, Installation and Inspection Supervision of Civil Nuclear Safety Equipment
HAF603
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