Sign In |Help & Support
ALL SECTORS
  • ALL SECTORS
  • GB(National Standard)
  • CB(Shipping)
  • CECS(Engineering Construction)
  • CJ(Urban Construction)
  • CY(News and Publication)
  • DB(Provincial Standard)
  • DL(Electricity & Power)
  • DZ(Geology & Mineralogy)
  • FZ(Spinning & Textile)
  • GA(Public Security)
  • HB(Aviation)
  • HG(Chemical Industry)
  • HJ(Environmental Protection)
  • JB(Machinery)
  • JC(Building Materials)
  • JG(Building & Construction)
  • JJ(Metering)
  • JT(Highway & Transportation)
  • LY(Forestry)
  • MT(Coal)
  • NB(Energy)
  • NY(Agriculture)
  • QB(Light Industry)
  • QC(Automobile & Vehicle)
  • QJ(Aerospace)
  • SH(Petrochemical)
  • SJ(Electronics)
  • SL(Water Resources)
  • SN(Commodity Inspection)
  • SY(Oil & Gas)
  • TB(Railway & Train)
  • YB(Ferrous Metallurgy)
  • YC(Tobacco)
  • YD(Telecommunication)
  • YY(Medical Device)
Database: 365,228(8 Aug 2026)

Pressurized water reactor nuclear power plant

Pressurized water reactor nuclear power plant, Total:440 items.

The international standard classification for "Pressurized water reactor nuclear power plant" includes: Nuclear power plants. Safety , Reactor engineering , Nuclear energy engineering , Radiation protection , Radiation measurements .

The Chinese standard classification for "Pressurized water reactor nuclear power plant" includes: Nuclear reactor and nuclear island equipment of nuclear power plant , Nuclear island of nuclear power plant , Nuclear facilities radiation safety , Radiation protection and monitoring in general , Radiation protection detection and evaluation , Power reactor , Technical management .


国家市场监督管理总局、中国国家标准化管理委员会

  • GB/T 41090-2021 General design requirements of pressurized water reactor nuclear power plants with active safety systems
  • GB/T 13976-2021 Radioactive source term of pressurized water reactor nuclear power plant for operation states
  • 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 40860-2021 Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants
  • GB/T 41140-2021 Analysis criterion for radiation source term of reactor core and spent fuel assembly in PWR nuclear power plant

General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China

  • GB/T 41584-2022 Requirements for hot performance test before initial fuel loading of pressurized water reactor nuclear power plants
  • GB/T 42141-2022 Radiation protection design criterion for nuclear island building under accident condition of presssurized water reactor nuclear power plant
  • GB/T 42292-2022 Occupational exposure dose assessment of pressurized water reactor nuclear power plant
  • GB/T 42143-2022 Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant
  • GB/T 13976-1992 Radioactive source term of PWR nuclear power plant for operational states
  • GB/T 42290-2022 Analysis and control specifications for airborne radioactive source term of pressurized water reactor nuclear power plant
  • GB/T 41585-2022 Specification of draw-up commissioning program for pressurized water reactor nuclear power plants
  • GB/T 42142-2022 Analysis criterion for radiation source term in auxiliary and secondary coolant system of pressurized water reactor nuclear power plant
  • GB/T 41587-2022 Requirements for cold performance test before initial fuel loading of pressurized water reactor nuclear power plants
  • GB/T 15761-1995 Design and construction rules for nuclear island systems of 2×600MW PWR nuclear power plants
  • GB/T 41576-2022 Requirements for unit performance test after initial fuel loading of pressurized water reactor nuclear power plants
  • GB/T 42291-2022 Radiation protection design criterion for doors and windows in controlled area of pressurized water reactor nuclear power plant
  • GB/T 17569-2013 Classification for the items of pressurized water reactor nuclear power pants
  • GB/T 17569-2013e Classification for the items of pressurized water reactor nuclear power plants
  • GB/T 41591-2022 Initial criticality tests for pressurized water reactor of nuclear power plants
  • GB/T 17569-1998 Classification for the Items of Pressurized Water Reactor Nuclear Power Plants
  • GB/T 13976-2008 Radioactive Source Term of PWR Nuclear Power Plant for Operational States

Professional Standard - Nuclear Industry

  • EJ/T 1123-2000 Specification for the magetic material of the CRDM for pressurized water reactor nuclear power plants
  • EJ 411-1989 Technical specifications for 20MnNiMo steel (S-271) forgings for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 328-1988 Design criteria for waste heat removal system of pressurized water reactor nuclear power plant
  • EJ/T 472-1999 Specification for the No.600 nickel base brazing filler metal of spacer grid of fuel assembly for pressurized water reactor nuclear power plants
  • EJ/T 1115-2000 Physics tests at low power for PWR nuclear power plant
  • EJ/T 509-1990 Protective coating for facilities and equipment inside the containment of a 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 1112-2000 Determination of the decontaminability of coatings for use in pressurized water reactor nuclear power plants
  • EJ/T 1022.9-1996 Ex-factory inspection and test of valve products in pressurized water reactor nuclear power plant
  • EJ 330-1988 Functional Design Criteria for Emergency Control Room in Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 318-1992 Reactor Design Criteria for Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 320-1998 General design criteria of reactor for pressurized water reactor nuclear power plants
  • EJ/T 1125-2000 Specification for primary piping ZG0Cr19Ni11Mo2 stainless steel cast pipe for pressurized water reactor nuclear power plants
  • EJ/T 1104-1999 Pressurized water reactor nuclear power plants 20HR steel plates for class 2,3 equipments
  • EJ/T 388-1989 Technical Specifications for Helium Leakage Detection of Steam Generators in 300 MW PWR Nuclear Power Plants
  • EJ/T 406-1999 Specification for primary system stainless steel elbow bent with intermediate frequency heating procedure for pressurized water reactor nuclear power plants
  • EJ/T 1022.8-1996 Technical requirements for installation and maintenance of valves in pressurized water reactor nuclear power plants
  • EJ 473-1989 Technical Specifications for Nickel-Fe-Chromium Alloy Full Heat Transfer Tubes for Steam Generators of 300,000-kilowatt Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1087-1998 Determination of chemical resistance of coatings used in pressurized water reactor nuclear power plants
  • EJ/T 394-1989 Technical conditions for the manufacture and acceptance of piping supports and hangers for the primary circuit system of a 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 386-1989 Safety-related ventilation duct support design regulations for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 459-1989 Installation and layout of safety-related sensors and transmitters for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 325-1988 Design criteria for reactor coolant system in pressurized water reactor nuclear power plant
  • EJ/T 330-1998 Design criteria for control room evacuation of PWR nuclear power plants
  • EJ/T 852-1994 Instrument pipelines penetrating the containment of a pressurized water reactor nuclear power plant
  • EJ/T 589-1999 Containment leaktightness test for pressurized water reactor of nuclear power plant
  • EJ/T 445-1989 Reactor and Power Distribution Abnormal Analysis of 300MW PWR Nuclear Power Plant
  • EJ/T 399-1989 Technical conditions for the installation of auxiliary equipment for the process system of the 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ 310-1988 PWR Nuclear Power Plant Engineering Terminology
  • EJ/T 669-2005 Criteria for chemical and volume control system design for pressurized water reactor nuclear powr plant
  • EJ 467-1989 Technical Specifications for Austenitic Stainless Steel Castings for 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1062-1998 Code of the design of steel safety-related structures for PWR nuclear power plant
  • EJ/T 324-1988 Design criteria for fuel-related components in pressurized water reactor nuclear power plants
  • EJ 464-1989 Technical specifications for nickel-chromium-iron alloy rods for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 469-1999 Specification for main bolting materials of safety class 1. equipments for pressurized water reactor nuclear power plants
  • EJ/T 1027.8-1996 Welding code for mechanical components of PWR nuclear islands Anticorrosion overlaying with nickel - base alloy
  • EJ/T 1029-1996 Code on design limits for fuel system of PWR nuclear power plants
  • EJ/T 1098-1999 Structural integrity test of containments for pressurised water reactor power plants
  • EJ/T 393-1989 300MW Pressurized Water Reactor Nuclear Power Plant Safety Four-Pipe Installation Technical Conditions for the Primary Circuit System
  • EJ/T 419-1989 300,000 kilowatts pressurized water reactor nuclear power plant safety secondary pump, tertiary pump coating process technical conditions
  • EJ/T 561-2000 Design criteria for safe shutdown of pressurized water reactor nuclear power plants
  • EJ/T 327-1988 Design criteria for containment sprinkler system in pressurized water reactor nuclear power plant
  • EJ/T 336-1988 Guidelines for layout of nuclear steam supply system in pressurized water reactor nuclear power plant
  • EJ/T 1027.5-1996 Welding code for mechanical components of PWR nuclear islands Welding of austenitic stainless steel
  • EJ/T 396-1989 300000KW PWR nuclear power plant - Test requirements for motor-driven valve operating test
  • EJ/T 449-1989 300MW PWR Nuclear Power Plant Reactor Main System Equipment and Installation Guidelines for Its Supports
  • EJ 472-1989 Specifications for No. 600 nickel-based brazing filler metal used for positioning grids of fuel assemblies in 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 1027.18-1996 Welding code for mechanical components of PWR nuclear islands Specification for equiapment production workshops
  • EJ/T 312-1988 Classification of operating and accident conditions in pressurized water reactor nuclear power plants
  • EJ/T 810-1994 One-time start-up of neutron source rods in pressurized water reactor nuclear power plants
  • EJ 314-1988 Safety Criterion for Accident Analysis of PWR Nuclear Power Plant
  • EJ/T 1022.7-1996 PWR nuclear power plant valve-Part 7: Packing, transportation and storage
  • EJ/T 383-1989 Transient regulations for design of reactor coolant system in 300 MW pressurized water reactor nuclear power plant
  • EJ/T 422-1989 Transistor selection and aging standards for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 635-1992 Design criteria for boron recovery system in pressurized water reactor nuclear power plant
  • EJ 341-1988 Water supply requirements for nuclear steam supply system of pressurized water reactor nuclear power plant
  • EJ/T 493-1989 300MW PWR Nuclear Power Plant Reactor Core Neutron Flux Measurement System Piping Design Regulations
  • EJ/T 1027.4-1996 Welding code for mechanical components of PWR nuclear islands Welding of carbon and low - alloy steel
  • EJ/T 387-1989 Cleaning Technical Conditions for the Commissioning Phase of the Primary Circuit System of 300MW PWR Nuclear Power Plant
  • EJ/T 480-1989 Construction Design Regulations for Primary Circuit System of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1103-1999 Pressurized water reactor nuclear power plants 20MnHR steel plates for class 2,3 equipments
  • EJ/T 492-1989 Quality Assurance of Protective Coatings for Nuclear Facilities of 300,000 KW PWR Nuclear Power Plant
  • EJ 463-1989 Technical conditions for GH169A alloy forging rods for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 333-1988 Design criteria for control rod drive mechanism in pressurized water reactor nuclear power plant
  • EJ/T 925-1995 Specifications for the design of concrete structures related to nuclear safety in pressurized water reactor nuclear power plants
  • EJ/T 1228-2008 Experiment demand for thermal tests on control rod drive line of PWR nuclear power plant
  • EJ/T 1027.14-1996 Welding code for mechanical components of PWR nuclear islands Welding procedure quelification of anticorrosion overlaying with austenitic stainless steel
  • EJ/T 505-1990 Radiographic Inspection of Welds in 300MW PWR Nuclear Power Plant
  • EJ/T 323-1998 Design criteria of fuel assembly for PWR nuclear power plant
  • EJ/T 712-1992 Technical requirements for the installation of reactor pressure vessels and related equipment in pressurized water reactor nuclear power plants
  • EJ/T 496-1989 Regulations for Design and Manufacture of Positioning Grid for 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 470-1999 Specification for cold rolled GH4169A alloy strip for pressurized water reactor nuclear power plants
  • EJ/T 385-1989 Containment Ventilation System of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1022.12-1996 Pneumatic Devices for Valves in PWR Nuclear Power Plants
  • EJ/T 471-1999 Specification for the GH4169A alloy "O" rings for pressurized water reactor nuclear power plants
  • EJ/T 408-1999 Technical specifications for 0Cr18Ni11Ti stainless steel hot-rolled steel pipes for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ 462-1989 Technical Specifications for Austenitic Stainless Steel "O" Rings for 300,000 KW Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 489-1989 Technical Conditions for Installation of Radiation Monitoring System in 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 500-1989 300,000-kilowatt pressurized water reactor nuclear power plant secondary neutron source components design and manufacturing technical conditions
  • EJ/T 1126-2000 Specification for safety - class. 2 bolting material used in pressure vessel for pressurized water reactor nuclear power plants
  • EJ/T 400-1989 Technical conditions for piping installation of the secondary circuit system of the reactor building of the 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ 316-1988 Design criteria for in-plant radiation zones in pressurized water reactor nuclear power plants
  • EJ/T 1134-2001 Design criteria for auxiliary Power systems of PWR nuclear power plants
  • EJ/T 1137-2001 Design Specification for PWR control rod drive mechanism
  • EJ/T 409-1999 Technical conditions for 0Cr18Ni11Ti stainless steel bars for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 450-1989 Regulations on On-Site Storage Management of Equipment and Materials of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ 401-1989 Stainless steel seamless steel pipe series for the primary circuit auxiliary system of the 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 389-1989 Technical Specifications for Voltage Stabilizers of 300MW PWR Nuclear Power Plant
  • EJ/T 455-1989 Types of Welded Joints of Stainless Steel Pipelines in 300MW Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 1027.7-1996 Welding code for mechanical components of PWR nuclear islands Anticorrosion overlaging with austenitic stainless steel
  • EJ 320-1988 General Design Guidelines for Reactor Structure of Pressurized Water Reactor Nuclear Power Plant
  • EJ 345-1988 Water chemistry specification for pressurized water reactor nuclear power plant
  • EJ/T 1022.6-1996 Valve Welding and Weld Acceptance of PWR Nuclear Power Plant
  • EJ/T 501-1990 Magnetic Particle Inspection of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 465-1999 Specification for martensitic age-stainless steel forging rods for pressurized water reactor nuclear power plants
  • EJ/T 668-1992 Design criteria for reactor coolant pressure boundary leak detection system for pressurized water reactor nuclear power plants
  • EJ/T 997-1996 Specifications for the construction of concrete structures related to nuclear safety in pressurized water reactor nuclear power plants
  • EJ/T 495-1989 Design regulations for fuel rods of 300,000,000 pressurized water reactor nuclear power plants
  • EJ/T 313-1988 Classification of Safety Levels of System Components in PWR Nuclear Power Plants
  • EJ/T 1027.6-1996 Welding code for mechanical components of PWR nuclear islands Welding for helerogeneous steel
  • EJ/T 416-1989 Regulations on Color Marking of Piping System of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 499-2004 Specification for design and manufacture of primary neutron source rod for pressurized water reactor nuclear power plant
  • EJ/T 508-1990 Specifications for protective coatings for 300 MW pressurized water reactor nuclear power plants
  • EJ/T 719-1992 Design criteria for fuel handling and storage systems in pressurized water reactor nuclear power plants
  • EJ/T 1027.9-1996 Welding code for mechanical components of PWR nuclear islands Hardfacing on Valve
  • EJ/T 671-1992 General technical specifications for pressurized water reactor nuclear power plant regulators
  • EJ/T 1027.13-1996 Welding code for mechanical components of PWR nuclear islands Welding procedure qualification of heterogeneous steel
  • EJ 322-1988 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
  • EJ/T 1022.5-1996 PWR nuclear power plant valve - Part 5: Technical conditions for austenitic stainless steel forgings
  • EJ/T 345-2005 The control of water chemistry for pressurized water reactor nuclear power plant
  • EJ/T 484-1989 Survey and assessment of soil corrosion in the 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 720-1992 Design criteria for the insulation layer of reactor pressure vessels and reactor coolant system piping and equipment in pressurized water reactor nuclear power plants
  • EJ/T 486-1999 Specification for super-low carbon chromium-nickel austenitic stainless steel cladding material for pressurized water reactor nuclear power plants
  • EJ/T 1111-2000 Test method for effects of gamma radiation on coatings for use in Pressurized water reactor nuclear power plants
  • EJ 486-1989 Technical specifications for ultra-low carbon Cr-Ni austenitic stainless steel surfacing materials for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 1022.2-1996 Technical specifications for carbon steel castings for pressurized water reactor nuclear power plant valves
  • EJ/T 392-1989 Specifications for Design of Supporting Components for Primary Equipment of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ 494-1989 Technical conditions for 1Cr13 steel compression elastic ring forgings for 300,000 kilowatts pressurized water reactor nuclear power plant
  • EJ 321-1988 Design criteria for internal components of pressurized water reactor nuclear power plants
  • EJ/T 1180-2005 Design Criteria for Installed Radiation Monitoring System in PWR Nuclear Power Plant Buildings
  • EJ/T 1063-1998 Code for the construction of steel safety-related structures for PWR nuclear power plant
  • EJ/T 475-1989 Design regulations for control rod guide tubes in 300 MW pressurized water reactor nuclear power plants
  • EJ/T 444-1989 Regulations on Nuclear Design Contents of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 417-1989 300 MW PWR nuclear power plant safety secondary pumps and tertiary pump packaging technical conditions
  • EJ/T 672-1992 General Technical Specifications for Steam Generators in Pressurized Water Reactor Nuclear Power Plants
  • EJ 481-1989 300,000-kilowatt pressurized water reactor nuclear power plant nickel-based composite spring wire technical conditions
  • EJ/T 712-2002 Installation requirements of reactor pressure vessel and its related equipment in PWR nuclear power plant
  • EJ 487-1989 Design and Construction Regulations for Prestressed Concrete Upper Containment of 300,000 Yuwa Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 338-1988 Design criteria for drainage and venting of nuclear steam supply system in pressurized water reactor nuclear power plant
  • EJ/T 1113-2000 Initial critical test in PWR nuclear power plant
  • EJ/T 747-1992 Guidelines for chemical decontamination of primary circuit systems and equipment in pressurized water reactor nuclear power plants
  • EJ/T 1022.17-1996 General technical requirements for surface treatment of valves in pressurized water reactor nuclear power plants
  • EJ/T 477-1989 Design rules for drag plug assembly of 300MW pressurized water reactor nuclear power plant
  • EJ/T 405-1989 General technical specifications for primary circuit stainless steel valves of 300 MW pressurized water reactor nuclear power plant
  • EJ/T 802-1993 X-ray photographic inspection method for weld seam of fuel assembly pipe seat in pressurized water reactor nuclear power plant
  • EJ/T 478-1989 300,000-kilowatt pressurized water reactor nuclear power plant reactor pressure vessel top cover assembly
  • EJ/T 504-1990 Regulations on Aging Screening and Derating of Safety-level Electronic Components in 300,000-kilowatt Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 883-2006 Design criteria for pressurized water reactor spent fuel storage facilities at nuclear power plant
  • EJ 456-1989 300 MW PWR Nuclear Power Plant Welder Skills Examination Rules
  • EJ/T 1027.19-1996 Welding code for mechanical components of PWR nuclear islands Qualification of welders and operators
  • EJ/T 461-1989 300,000-kilowatt pressurized water reactor nuclear power plant cable, screen, platform, plate numbering regulations
  • EJ/T 1022.18-1996 PWR nuclear power plant valve-Part 22: Product cleaning rules
  • EJ/T 1022.16-1996 Technical conditions for NCh valves in pressurized water reactor nuclear power plants
  • EJ/T 502-1990 Liquid Penetration Inspection of 300MW PWR Nuclear Power Plant
  • EJ/T 1022.3-1996 Technical specifications for stainless acid-resistant steel castings for pressurized water reactor nuclear power plant valves
  • EJ 406-1989 Technical specifications for stainless steel intermediate frequency elbows in the primary circuit system of 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 732-1992 Evaluation criteria for pressurized thermal shock of reactor pressure vessels in pressurized water reactor nuclear power plants
  • EJ/T 321-1998 Design criterion of reactor internals for pressurized water reactor nuclear power plants
  • EJ/T 1022.1-1996 PWR nuclear power plant valve - Part 1: General rules for design and manufacture
  • EJ 465-1989 Technical conditions for martensitic stainless steel forged rods for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 1022.15-1996 PWR nuclear power plant valve-Part 15: Seismic identification test
  • EJ 468-1989 Technical conditions for 0Cr18Ni11Ti stainless steel forgings for 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 497-1989 300,000 kW pressurized water reactor nuclear power plant fuel assembly design regulations
  • EJ/T 479-1989 Selection and Design Regulations for Control Valves of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 446-1989 300MW PWR nuclear power plant reactor physical start-up test
  • EJ/T 398-1989 Technical Specifications for Voltage Stabilizer Electric Heater of 300MW PWR Nuclear Power Plant
  • EJ/T 421-1989 Nuclear-grade high-efficiency iodine adsorber for 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 457-1989 Specifications for Manual Arc Welding Electrodes for Safety Level 1 Pressure Vessels of 300,000 KW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1189-2005 Code for main steam system design of pressurized water reactor nuclear power plant
  • EJ/T 473-2000 Specification for nickel-iron-cromium alloy tube for nuclear steam generator for pressurized water reactor nuclear power plant
  • EJ/T 474-2000 Specification for reactor pressure vessel metal insulation for pressurized water reactor nuclear power plants
  • EJ/T 316-2001 Design Criterion of Radiation Zoning
  • EJ/T 468-1999 Specification for stainless steel forging for pressurized water reactor nuclear power plants
  • EJ/T 1027.10-1996 Welding code for mechanical components of PWR nuclear islands Repair of weld defects by welding
  • EJ/T 322-1994 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
  • EJ/T 1122-2000 Specification for SG6 Co-based alloy of the CRDM for pressurized water reactor nuclear power plants
  • EJ/T 339-1988 Design criteria for safety valve and pressure relief valve piping system in pressurized water reactor nuclear power plant
  • EJ/T 1027.12-1996 Welding code for mechanical components of PWR nuclear islands Welding procedure qualification of austenitic stainless steel
  • EJ/T 1027.3-1996 Welding code for mechanical components of PWR nuclear islands Storage and use management of the welding materials
  • EJ/T 507-1990 Design and Construction Regulations for Concrete Structures Related to Nuclear Safety in 300MW Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 1027.2-1996 Welding code for mechanical components of PWR nuclear islands Qualification of welding materials
  • EJ/T 1179-2005 Design criteria for engineered safety features of pressurezed water reactor plants
  • EJ 485-1989 Technical specifications for 18MnNiMo steel thick plates for safety first-class pressure vessels of 300,000 pressurized water reactor nuclear power plants
  • EJ 323-1988 Fuel Assembly Design Criteria for Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 1027.1-1996 Welding code for mechanical components of PWR nuclear islands Accepance of welding material
  • EJ 474-1989 300,000-kilowatt pressurized water reactor nuclear power plant Reactor Pressure Vessel Metal Foil Insulation Layer Technical Specifications
  • EJ/T 816-1994 Design criteria for emergency core cooling pits in pressurized water reactor nuclear power plants
  • EJ/T 506-1990 Design regulations for control rod drive mechanism of 300 MW pressurized water reactor nuclear power plant
  • EJ/T 1045-1997 The requirement of draw-up commissioning program for PWR nuclear power plant
  • EJ/T 483-1989 Guidelines for Preparation of Technical Documentation for Reactor Pressure Vessels of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ 412-1989 Technical conditions for 16MnHR steel plates for 300,000-kilowatt pressurized water reactor nuclear power plants
  • EJ/T 1041-1996 Code on the in-service inspections of mechanical components of pressurized water reactor nuclear islands
  • EJ 470-1989 Technical conditions for GH169A alloy cold-rolled strip for 300,000-kilowatt pressurized water reactor nuclear power plant
  • EJ/T 1022.11-1996 PWR nuclear power plant valve-Part 11: Electric actuator
  • EJ 471-1989 GH169A Alloy "O" Ring Technical Specifications for 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1027.15-1996 Welding code for mechanical components of PWR nuclear islands Welding procedure qualification of anticorrosion overlaying with nickel-base alloy
  • EJ/T 451-1989 Code for Regional Cathodic Protection Design of Underground Metal Structures in 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 412-1999 Specification for 16MnHR steel plate of safety class 2 pressure vessel for pressurized water reactor nuclear power plants
  • EJ/T 447-1989 Technical Conditions for Manufacture and Acceptance of Steam Generators in 300MW Pressurized Water Reactor Nuclear Power Plants
  • EJ 469-1989 Technical Specifications for Main Bolt Materials of Safety Level 1 Equipment of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 819-1994 Character codes and graphic symbols for radiation monitoring design of pressurized water reactor nuclear power plants
  • EJ/T 319-1992 Thermal-hydraulic Design Criteria for Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 720-2008 Design criterion for the thermal insulation of reactor vessel and reactor coolant pipings and equipments of PWR nuclear power plants
  • EJ/T 494-1999 Specification for reactor internals compression spring-ring forging for pressurized water reactor nuclear power plants
  • EJ/T 340-1988 Design criteria for interface between nuclear steam supply system and steam turbine building in pressurized water reactor nuclear power plant
  • EJ/T 1138-2001 Rules for non-destructive examination of welds of containment leak-resistant liner of PWR nuclear island
  • EJ/T 779-1993 Predicted transient analysis requirements for PWR nuclear power plants that fail to emergency shut down
  • EJ/T 503-1990 300MW Pressurized Water Reactor Nuclear Power Plant Reactor Internals Design and Manufacturing Specifications
  • EJ/T 344-1988 Cable laying and isolation guidelines for pressurized water reactor nuclear power plants
  • EJ/T 460-1989 300,000-kilowatt pressurized water reactor nuclear power plant and the instrument signal pipeline connected with the safety-related process system
  • EJ/T 341-1998 PWR NP NSSS makeup water requirements
  • EJ/T 453-1989 Technical conditions for painting, packaging and transportation of pressure vessels of 300,000-kilowatt pressurized water reactor nuclear power plant safety level 2 and 3
  • EJ/T 390-1989 300MW Pressurized Water Reactor Nuclear Power Plant Safety Level 2 Centrifugal Pump Specifications
  • EJ/T 476-1989 Technical Specifications for Burnable Poisons in 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1012-1996 Specifications for the manufacture of nuclear island machinery and equipment for pressurized water reactor nuclear power plants
  • EJ/T 384-1989 300MW Pressurized Water Reactor Nuclear Power Plant Reactor Coolant Main Piping Installation Technical Conditions
  • EJ/T 498-1989 Design and Manufacturing Technical Specifications for Control Rod Components of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 490-1989 300MW PWR Nuclear Power Plant Radiation Monitoring System Pipeline and Equipment Cleaning Specifications
  • EJ 317-1988 Radiation Shielding Design Criteria for Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 317-1998 Design Criterion of Radiation Shield in the PWR Nuclear Power Plant
  • EJ/T 482-1989 Strength Analysis of Piping System in 300MW PWR Nuclear Power Plant
  • EJ/T 342-1988 Requirements for Nitrogen, Hydrogen and Oxygen Supply in Nuclear Steam Supply System of PWR Nuclear Power Plant
  • EJ/T 395-1989 Technical Specifications for Valve Electric Devices of 300MW PWR Nuclear Power Plant
  • EJ/T 391-1989 300 MW PWR Nuclear Power Plant Safety Level 3 Centrifugal Pump Technical Specifications
  • EJ/T 608-1991 General specifications for transport containers for new fuel assemblies in pressurized water reactor nuclear power plants
  • EJ/T 817-1994 Regulations on packaging, transportation, handling and storage of new fuel assemblies in pressurized water reactor nuclear power plants

Professional Standard - Energy

  • NB/T 20304-2014 Technical guideline for installation of reactor protection system of pressured water reactor nuclear power plants
  • NB/T 20260-2014 Design criteria for residual heat removal system of pressurized water reactor nuclear power plants
  • NB/T 20174-2012 Technical Specification for Onsite Manufacture and Acceptance of Carbon Steel & Stainless Steel Tanks of PWR Nuclear Island
  • NB/T 20110-2012 Technical Regulation for Installation of PWR Nuclear Power Auxiliary System Equipment
  • NB/T 20057.1-2012 Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 1: Nuclear Design
  • NB/T 20008.8-2012 Other Materials for Pressurized Water Reactor Nuclear Power Plants - Part 8: Hot Extruded Nickel-chromium-iron Alloy Pipes
  • NB/T 20177-2012 Design Criteria for Component Cooling Water System of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20178-2012 Design Criteria of Nuclear Sampling System of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20007.16-2012 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants - Part 16: Classes 2 and 3 Martensitic Stainless Steel Forgings
  • NB/T 20161-2012 Installation and Commissioning Technical Guideline for Ex-core Neutron Flux Measuring System for Pressurized Water Reactor of Nuclear Power Plants
  • NB/T 20287-2014 Design and fabrication rules for refueling machine of PWR nuclear power plants
  • NB/T 20010.15-2010 PWR Nuclear Power Plant Valve - Part 15: Specification of Spiral Wound Gasket with Flexible Graphite
  • NB/T 20103-2012 Accident Analysis and Safety Criteria for Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20125-2012 Construction Specification of the Foundation Grouting for PWR Safety Important Facility
  • NB/T 20005.34-2015 Carbon steel and low alloy steel for pressurized water reactor nuclear power plant-Part 34: Carbon steel shear studs for containment vessel
  • NB/T 20251-2013 Design criteria for normal air cleaning units in PWR nuclear power plants
  • NB/T 20008.17-2012 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 17: Classes 2 and 3 Unalloyed and Alloy Ductile Iron Castings
  • NB/T 20005.31-2015 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants-Part 31:15Mn forgings for containment vessel
  • NB/T 20009.2-2010 Welding Material for Pressurized Water Reactor Nuclear Power Plants - Part 2: Low Alloy Steel Covered Electrodes for Classes 1, 2, 3, Components
  • NB/T 20010.11-2010 PWR Nuclear Power Plant Valve - Part 11: Electric Actuator
  • NB/T 20057.3-2012 PWR Nuclear Power Plants Reactor System Design - Core - Part 3: Fuel Assembly
  • NB/T 20261-2014 Design criteria for emergency core cooling system of pressurized water reactor nuclear power plants
  • NB/T 20045-2011 Technical Regulation for Construction and Acceptance of Reactor Vessel Installation in PWR Nuclear Power Plant
  • NB/T 20233-2013 Cleaning & Clear Degree Requirements for Nuclear Steam Supply System of PWR Nuclear Power Plants
  • NB/T 20007.41-2015 Stainless steel for pressurized water reactor nuclear power plants Part 41:austenitic stainless steel seamless pipes used for reactor vessel internals
  • NB/T 20005.16-2012 Carbon Steel and Low Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 16: Elbow for Main Steam System
  • NB/T 20044-2011 Technical Regulation for Construction and Acceptance of Reactor Internals Installation in PWR Nuclear Power Plant
  • NB/T 20007.31-2015 Stainless steel for pressurized water reactor nuclear power plants-Part 31:022Cr19Ni10 stainless steel forgings used for containment vessel
  • NB/T 20008.15-2012 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 15: Titanium Plate for Use in the Fabrication of Class 3 Heat Exchanger Plates
  • NB/T 20244-2013 Plugging Guideline for Heat Transfer Tube of PWR Steam Generator
  • NB/T 20010.3-2010 PWR Nuclear Power Plant Valve - Part 3: Specification of Stainless Steel Casting
  • NB/T 20005.33-2015 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants-Part 33:15Mn steel pipes for containment vessel
  • NB/T 20007.6-2012 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants - Part 6: Controlled Nitrogen Content Austenitic Stainless Steel Plate for Reactor Internal
  • NB/T 20131-2012 Design Criteria for Emergency Core Cooling Sump of Pressurized Water Reactors Nuclear Power Plants
  • NB/T 20232-2013 Code for Design of Fuel Loading & Storage System of PWR Nuclear Power Plants
  • NB/T 20132-2012 Design Requirements of Personnel Airlock for Containment in Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20006.5-2012 Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 5: Mn-Ni-Mo Steel Forgings for Reactor Pressure Vessel Heads
  • NB/T 20280-2014 Design criteria of boron recycle system for PWR nuclear power plants
  • NB/T 20354.2-2015 Design and manufactering specification of steam turbine rotor for pressurized water reactor nuclear power plant-Part 2:Shrunk rotor
  • NB/T 20008.25-2015 Other material for pressurized water reactor nuclear power plants Part 25: GH4169 alloy wires for reactor vessel internals
  • NB/T 20252-2013 Code for Design of Air Cleaner in PWR Nuclear Power Plants
  • NB/T 20211-2013 Qualification Procedure for Safety Class Medium Voltage Motors of PWR Nuclear Power Plants
  • NB/T 20222-2013 Guide for the Aging of PWR Steam Generator
  • NB/T 20007.35-2015 Stainless steel for pressurized water reactor nuclear power plants-Part 35:06Cr18NillTi stainless steel plates used for containment vessel mechanical penetrations
  • NB/T 20006.31-2015 Alloy steel for pressurized water reactor nuclear power plants - Part 31: 10MnNiMo steel plates for contaiment vessel
  • NB/T 20005.11-2012 Carbon Steel and Low Alloy Steel for Pressurized Water Reactor Nuclear Power Plant - Part 11: Seamless Pipes for Classes S1 and S2 Supports
  • NB/T 20273-2014 Design criteria of radioactive drain and vent for PWR nuclear power plant
  • NB/T 20007.33-2015 Stainless steel for pressurized water reactor unclear power plants-Part 33:015Cr17Ni12Mo2N stainless steel forged pipes for reactor coolant piping
  • NB/T 20008.21-2015 Other material for pressurized water reactor nuclear power plants-Part 21:GH4169 alloy bars used for CRDM
  • NB/T 20008.5-2012 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 5: Class 1 and 2 Hot Rolled Nickel-Chromium-Iron Alloy Plates
  • NB/T 20046-2011 Technical Regulation for Construction and Acceptance of Reactor Internals Installation in PWR Nuclear Power Plant
  • NB/T 20334-2015 General requirements for noise analysis of reactor and primary loop in pressurized water reactor nuclear power plant
  • NB/T 20291-2014 Design criteria for passive PWR NPP normal residual heat removal system
  • NB/T 20354.3-2015 Design and manufactering specification of steam turbine rotors for pressurized water reactor nuclear power plant - Part 3: Welded rotor
  • NB/T 20007.34-2015 Stainless steel for pressurized water reactor nuclear power plants-Part 34:03Cr22Mn5Ni2MoCuN duplex stainless steel plates for modules
  • NB/T 20184-2012 General Specification on Transport Vessel for Fresh Fuel Assembly of PWR Nuclear Power Plants
  • NB/T 20009.14-2013 Welding Material for Pressurized Water Reactor Nuclear Power Plants - Part 14: Hard Facing Welding Consumables for Classes 1|| 2|| 3 Components
  • NB/T 20189-2012 Interface Design Criteria Concerning Nuclear Steam Supply System and Turbine Building of Pressured Water Reactor Nuclear Power Plant
  • NB/T 20142-2012 Guide for Chemical Decontamination of Primary Loop System and Components of PWR Nuclear Power Plants
  • NB/T 20010.7-2010 PWR Nuclear Power Plant Valve - Part 7: Specification of Packaging, Transport and Storage
  • NB/T 20007.40-2015 Stainless steel for pressurized water reactor nuclear power plants-Part 40:austenitic stainless steel forgings used for reactor vessel internals
  • NB/T 20327.1-2015 Special doors of pressurized water reactor nuclear power plant Part 1: Design
  • NB/T 20333-2015 Design criteria of safety depressurization and venting system for primary loop of pressurized water reactor nuclear power plant
  • NB/T 20151-2012 Guideline for Preparing Ageing Management Programme of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20010.14-2010 PWR Nuclear Power Plant Valve - Part 14: Specification of Flexible Graphite Packing
  • NB/T 20108-2012 Technical Regulation of Containment Penetration Installation in PWR Nuclear Power Plant
  • NB/T 20224-2013 Specification for Design & Fabrication of Control Rod Drive Mechanism of PWR Nuclear Power Plants
  • NB/T 20008.24-2015 Other material for pressurized water reactor nuclear power plants Part 24: GH4145 alloy bars for reactor vessel internals
  • NB/T 20169-2012 Qualification Procedure for Auxiliary Reed Water Turbine-driven Pump of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20662-2023 Classification of operating conditions of pressurized water reactor nuclear power plants
  • NB/T 20005.5-2013 Carbon Steel and Low Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 5: Classes 1, 2 and 3 Pressure Retaining Castings
  • NB/T 20008.4-2012 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 4: Forged or Rolled Classes 1, 2 and 3 Nickel-Chromium-Iron Alloy Parts
  • NB/T 20231-2013 Code for Design of Safety Precautions of PWR Nuclear Power Plants
  • NB/T 20164-2012 Qualification Procedure for Auxiliary Feed Water Motor-driven Pump of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20325.2-2014 Prestressing technology specification for safety containments of PWR nuclear power plants-Part2:test
  • NB/T 20007.5-2010 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants - Part 5: Classes 1, 2, 3 Austenitic Stainless Steel Plates
  • NB/T 20006.16-2013 Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 16: Mn-Ni-Mo Steel Plates for Pressurizer Supports
  • NB/T 20345-2015 Technical specification for installation and test of faulted fuel sipping device in PWR nuclear power plants
  • NB/T 20167-2012 Qualification Procedure for Isolation Valve of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20124-2012 Code for Acceptance of Construction of Biological Shielding Concrete of PWR Nuclear Power Plant
  • NB/T 20057.4-2012 PWR Nuclear Power Plants Reactor System Design - Core - Part 4: Core Components
  • NB/T 20010.1-2010 PWR Nuclear Power Plant Valve - Part 1: General Standard for Design and Manufacture
  • NB/T 20010.8-2010 PWR Nuclear Power Plant Valve - Part 8: Specification of Installation and Maintenance
  • NB/T 20353-2015 Erection technical regulations for loose parts and vibration monitoring system for PWR nuclear power plants
  • NB/T 20022-2010 The Hoisting Technical Specification for Dome of Reactor Building of PWR Nuclear Power Plant
  • NB/T 20057.2-2012 Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core- Part 2: Thermal Hydraulic Design Criteria
  • NB/T 20311-2014 Design criteria for containment spray system of pressurized water reactor nuclear power plants
  • NB/T 20275-2014 Stud welding specification for pressurized water reactor nuclear power plants
  • NB/T 20315-2014 Design and fabrication specification for steam generator of pressurized water reactor nuclear power plants
  • NB/T 20258.1-2014 PWR Nuclear power plant module design requirements - Part 1:Mechanical module
  • NB/T 20007.32-2015 Stainless steel for pressurized water reactor nuclear power plants-Part 32:022Cr19Ni10 stainless steel seamless pipes for containment vessel
  • NB/T 20194-2012 Design Criterion of Radiation Shield in the PWR Nuclear Power Plant
  • NB/T 20081-2012 Qualification Procedure for Class 1E Transformer Applied in Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20330-2015 Document code for passive PWR nuclear power plant
  • NB/T 20010.12-2010 PWR Nuclear Power Plant Valve - Part 12: Pneumatic Actuator
  • NB/T 20269-2014 Design and fabrication specification for reactor coolant pump of pressurized water ractor nuclear power plant
  • NB/T 20354.1-2015 Design and manufactering specification of steam turbine rotors for pressurized water reactor nuclear power plant-Part1:Integral rotor
  • NB/T 20113-2012 Technical Regulation for Construction of HVAC Installation in PWR Nuclear Power Plant
  • NB/T 20388-2016 Specifications for construction and acceptance for openings sealing in nuclear island of PWR nuclear power plant
  • NB/T 20005.32-2015 Carbon steel and low alloy steel for pressurized water reactor nuclear power plants. Part 32: 15MnHR steel plates for containment vessel
  • NB/T 20005.9-2010 Carbon Steel and Low Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 9: Seamless Steel Pipes for Classes 2, 3 Piping
  • NB/T 20133.1-2012 Specifications for Protective Coatings Used in Pressurized Water Reactor Nuclear Power Plants - Part 1: General Requirements
  • NB/T 20007.42-2015 Stainless steel for pressurized water reactor nuclear power plants Part 42: precipitation-hardening stainless steel bars for reactor vessel internals
  • NB/T 20007.19-2013 Stainless Steel for Pressurized Water Reactor Power Plants - Part 19: Classes 1|| 2 and 3 Pressure-retaining Martensitic Stainless Steel Castings
  • NB/T 20325.1-2014 Prestressing technology specification for safety containment of PWR nuclear power plants-Part 1:Material
  • NB/T 20127-2012 Technical Requirements for Embedment Parts Manufacture and Installation of PWR Nuclear Power Plant
  • NB/T 20008.22-2015 Other material for pressurized water reactor nuclear power plants-Part 22: GH4145 alloy bars used for CRDM
  • NB/T 20266-2014 Specification for design of condensate polishing,chemical reagents injection and secondary sampling system for PWR nuclear power plants
  • NB/T 20253-2013 Code for the Cleaning of PWR Nuclear Power Plant during Installation and Commissioning
  • NB/T 20187-2012 Design Criteria for Reactor Coolant System in Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20126-2012 Specifications for Construction and Acceptance of Caulking of PWR Nuclear Island Plant
  • NB/T 20129-2012 General Technical Regulation for Installation, Test and Acceptance of Emergency Diesel Generator of Nuclear Island in Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20111-2012 General Technical Regulation of Safety-related Valves Installation in PWR Nuclear Power Plant
  • NB/T 20285-2014 General requirements of reactor system design for pressurized water reactor nuclear power plants
  • NB/T 20188-2012 Design Criteria for Essential Service Water System for Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20158-2012 Specification for Volute Concrete Construct of Circulating Water Pump of Pressurized Water Reactors Nuclear Power Plants
  • NB/T 20109-2012 Technical Specification of Neutron Flux Guide Tube Installation in Reactor Building for PWR Nuclear Power Plant
  • NB/T 20240-2013 Physical Start-up Test of Nuclear Power Plants after Reloading
  • NB/T 20171-2012 Qualification Procedure for Safety Class 3 Pump of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 11234-2023 Guidelines for pressure piping supervision and management of conventional island in pressurized water reactor nuclear power plant
  • NB/T 20112-2012 Technical Regulation of the Cable Terminal Connection in the Reactor Building for PWR Nuclear Power Plant
  • NB/T 20002.5-2013 Welding Code for Mechanical Components of PWR Nuclear Islands - Part 5: Technical Qualification for Production Workshops
  • NB/T 20104-2012 Analysis Requirement for Anticipated Transient without Scram on Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20009.12-2013 Welding materials for pressurized water reactor nuclear power plants. Part 12: Nickel-based alloy strip cladding with flux for class 1 components
  • NB/T 20097-2012 Concrete Containment Functional Design Requirements for PWR Nuclear Power Plant
  • NB/T 20115-2012 Technical Regulation for Construction and Acceptance of Reactor Pressure Vessel Head Installation in PWR Nuclear Power Plants
  • NB/T 20009.28-2015 Welding material for pressurized water reactor nuclear power plants-Part 28: Nickel alloy welding electrodes for safety-related components
  • NB/T 20091-2012 Inspection Guide for the Turbine of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20133.6-2012 Specifications for Protective Coatings Used in Pressurized Water Reactor Nuclear Power Plants - Part 6: Coating Operation
  • NB/T 20341-2015 Technical specification for nuclear island building hole blocking material and caulking material of PWR nuclear power plants
  • NB/T 20346-2015 The technical specification of fabrication and assemble for polar crane beam in PWR nuclear power plants
  • NB/T 20002.1-2013 Welding Code for Mechanical Components of PWR Nuclear Islands - Part 1: General Requirements
  • NB/T 20268-2014 Rules for the design of PWR unclear power plant safety and relief valve piping
  • NB/T 20008.6-2012 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 6: Hot Rolled Nickel-Chromium-Iron Alloy Plates
  • NB/T 20262-2014 Design criteria for steam generator blowdown system of pressurized water reactor nuclear power plants
  • NB/T 20332-2015 Constraction requirements for prestressed concrete containments for pressure water reator nuclear power plants
  • NB/T 20064-2012 Installation and Test Requirement of In-core Instrumentation System in Pressured Water Reactor Nuclear Power Plant
  • NB/T 25038-2014 Circulating water system commissioning program rule of PWR
  • NB/T 20078-2012 Qualification Procedure for Safety-related Pneumatic Control Valve of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20278-2014 Design criteria for emergency feedwatcr system of pressurized water reactor nuclear power plants
  • NB/T 20165-2012 Qualification Procedure for Residual Heat Removal Pump of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20309-2014 General design requirements of pressurized water reactor nuclear power plants with active safety systems
  • NB/T 20163-2012 Qualification Procedure for Containment Spray Pump and Low Head Safety Injection Pump of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20002.2-2013 Welding Code for Mechanical Components of PWR Nuclear Islands - Part 2: Acceptance for Welding Filler Materials
  • NB/T 20239-2013 Guidelines on Drafting Outlines for Commissioning of PWR Nuclear Power Plants
  • NB/T 20008.12-2010 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 12: Forged or Rolled Bars for Classes 1, 2, 3 Bolts and Nuts
  • NB/T 20168-2012 Qualification Procedure for Check Valve of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20002.4-2013 Welding Code for Mechanical Components of PWR Nuclear Islands - Part 4: Qualification of Filler Materials
  • NB/T 20008.1-2012 Other Material for Pressurized Water Reactor Nuclear Power Plants - Part 1: Alloy Steel Forgings for Use in Reactor Coolant System Supports
  • NB/T 20010.5-2010 PWR Nuclear Power Plant Valve - Part 5: Specification of Austenitic Atainless Steel Forging
  • NB/T 20010.13-2010 PWR Nuclear Power Plant Valve - Part 13: Specification of Non Classified Valve for Nuclear Device
  • NB/T 20329-2015 System/Equipment code for passive PWR nuclear power plant
  • NB/T 20154-2012 Guideline of Ageing Management for PWR Reactor Pressure Vessels
  • NB/T 20010.9-2010 PWR Nuclear Power Plant Valve - Part 9: Final Examination and Test in Manufactory
  • NB/T 20012-2010 Design Requirements for Nuclear Safety Related Concrete Structure for Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20009.3-2010 Welding Material for Pressurized Water Reactor Nuclear Power Plants - Part 3: Stainless Steel Covered Electrodes for Classes 1,2,3 Components
  • NB/T 20166-2012 Qualification Procedure for Charging Pump of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20176-2012 Design Requirement for Hydrogen Supply Nitrogen Supply Oxygen Supply Carbon Dioxide Supply System of PWR Nuclear Power Plant
  • NB/T 20212-2013 Qualification Procedure for Safety Class 380V Motors of PWR Nuclear Power Plants
  • NB/T 20006.15-2013 Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 15: Mn-Ni-Mo Steel Plates for Pressure-retaining Boundaries
  • NB/T 20011-2010 Design Requirements for Nuclear Safety Related Steel Structure for Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20236-2013 Rules for Non-destructive Examination of Welds of Containment Leak-resistant Liner of PWR Nuclear Power Plants
  • NB/T 20017-2010 Structural Integrity Test of Containments for Pressurized Water Reactor Power Plants
  • NB/T 20310-2014 Design requirements for structures of ultimate heat sink for pressurized water reactor nuclear power plants
  • NB/T 25116-2020 Directive of turbine steam admission and no-load operation test for pressurized water reactor nuclear power plants
  • NB/T 20101-2012 Analysis Requirement for Rod Ejection Accidents of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20303-2014 Design requirements for prestressed concrete containments for pressure water reactor nuclear power plants
  • NB/T 20192-2012 General Requirements for Pilot Operated Safety Valves of Pressurized Water Reactor Nuclear Power Plant
  • NB/T 20099-2012 Analysis Demand for Loss-of-coolant Accident of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20098-2012 Design Criteria for Containment Hydrogen Control System of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20007.8-2010 Stainless Steel for Pressurized Water Reactor Nuclear Power Plants - Part 8: Class 1, 2, 3 Austenitic Stainless Steel Seamless Pipes
  • NB/T 20221-2013 Corrosion Examination for Secondary Circuit Thermal Power Equipment of PWR Nuclear Power Plants
  • NB/T 20010.6-2010 PWR Nuclear Power Plant Valve - Part 6: Specification for Fastener
  • NB/T 20032-2010 Evaluation Rule of Pressurized Thermal Schock for Reactor Pressure Vessel of PWR NPP
  • NB/T 20100-2012 Principles for Main Primary System and Main Steam System Overpressure Analysis of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20327.2-2015 Special doors of pressurized water reactor nuclear power plant Part 2:Manufacture
  • NB/T 20191-2012 Accessibility Criteria for In-service Inspections in Structural Design of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20002.6-2013 Welding Rules for Mechanical Components of PWR Nuclear Islands - Part 6: Production Welds
  • NB/T 20035-2011 Categorization of Conditions of PWR Nuclear Power Plants
  • NB/T 20005.3-2012 Carbon Steel and Low Alloy Steel for Pressurized Water Reactor Nuclear Power Plants - Part 3: Forgings for Classes 2, 3 Auxiliary Pump Shafts
  • NB/T 20325.3-2014 Prestressing technology specification for safety containments of PWR nuclear power plants-Part 3:Construction
  • NB/T 20107-2012 Technical Regulation for Construction of Reactor Coolant Pump Installation in PWR Nuclear Power Plant
  • NB/T 20002.7-2013 Welding Code for Mechanical Components of PWR Nuclear Islands - Part 7: Hardfacing
  • NB/T 20141-2012 Packaging, Transportation, Loading & Unloading and Storage of Fresh Fuel Assembly for PWR Nuclear Power Plant
  • NB/T 20008.14-2013 Other Materials for Pressurized Water Reactor Nuclear Power Plants - Part 14: Nickel-chromium-iron Alloy Wires of Springs

Professional Standard - Environmental Protection

  • HJ 842-2017 Emergency-Related Parameters for Presurrized Water Reactor Nuclear Power Plants

Group Standards of the People's Republic of China

  • T/BSRS 085-2021 Technical specification for evaluation of nuclear design and analysis software for pressurized water reactor nuclear power plants
  • T/BSRS 083-2021 Technical specification for safety software safety evaluation of non-breach accident systems in PWR nuclear power plants
  • T/BSRS 084-2021 Technical Specification for Best Estimated LB-LOCA system analysis Code Assessment of PWR Nuclear Power Plant
  • T/BSRS 023-2020 Technical specification for radiation zone adjustment during power operation of PWR nuclear power plant
  • T/BSRS 082-2021 Technical Specification for Conservative LB-LOCA-analysis code Assessment of PWR Nuclear Power Plant
  • T/BSRS 053-2021 Technical Specification for System Equipment Source Term Code Assessment of PWR Nuclear Power Plant
  • T/ZZB 0751-2018 Nuclear class bolts and studs for pressurized water reactor nuclear power plants

国家能源局

  • NB/T 10666-2021 Technical requirements for instrumentation and control equipment earthing and shielding in conventional island of nuclear power plants
  • NB/T 20436-2017 Water chemistry for pressurized water reactor nuclear power plant
  • NB/T 20577-2019 Technical specification for installation and acceptance inspection of canned reactor coolant pump in PWR nuclear power plant
  • NB/T 20550-2019 Commissioning technical guideline for safety class digital control system of PWR nuclear power plants
  • NB/T 20434-2017 Initial loading test for pressurized water reactor of nuclear power plant
  • NB/T 20574-2019 Terminology of commissioning for PWR nuclear power plants
  • NB/T 20009.36-2018 Welding material for pressurized water reactor nuclear power plants -Part 36: Electrodes for gas shielded are welding for containment vessel
  • NB/T 20325.4-2018 Prestressing technology specification for safety containments of PWR nuclear power plants-—Part4:Monitoring
  • NB/T 20435-2017 Physics tests for pressurized water reactor of nuclear power plants commissioning startup