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Database: 365,228(8 Aug 2026)

Ruijin Nuclear Power Plant

Ruijin Nuclear Power Plant, Total:224 items.

The international standard classification for "Ruijin Nuclear Power Plant" includes: Flat steel products and semi-products , Steels pipes and tubes for specific use , Cables , Stainless steels .

The Chinese standard classification for "Ruijin Nuclear Power Plant" includes: Steel sheet and strip , Steel tube and cast iron pipe , Cable and its accessory , Profile steel and deformed steel .


国家市场监督管理总局、中国国家标准化管理委员会

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

  • GB/T 31941-2015 Non-nuclear nuclear power plant safety level carbon and alloy steel welded steel pipe
  • GB/T 22577-2008 Class 1E cables for nuclear power generating stations - General requirements
  • GB 30814-2014 Steel plates of carbon steel and low alloy steel for nuclear power plants
  • GB/T 41754-2023 Duplex stainless steel plate used for nuclear power plants
  • GB 24512.2-2009 Seamless steel tubes and pipes for nuclear power plant.Part 2:Alloy steel seamless tubes and pipes

中华人民共和国国家质量监督检验检疫总局、中国国家标准化管理委员会

  • GB/T 36027-2018 Austenitic stainless steel bars for nuclear power plants
  • GB/T 30814-2014 Steel plates of carbon steel and low alloy steel for nuclear power plants
  • GB/T 24512.2-2009 Seamless steel tubes and pipes for nuclear power plant―Part 2:Alloy steel seamless tubes and pipes

Jiangxi Provincial Standard of the People's Republic of China

未注明发布机构

  • ANSI/ANS 54.1-2020 Nuclear Safety Criteria and Design Process for Sodium Fast Reactor Nuclear Power Plants
  • CSA N293-2023 Fire protection for nuclear power plants

Group Standards of the People's Republic of China

Professional Standard - Machinery

  • JB/T 12429-2015 Class 1 E heat-shrinkable power cable splices in nuclear power generating stations
  • JB/T 12214-2015 Polar cranes for nuclear power plants

Gansu Provincial Standard of the People's Republic of China

American Welding Society (AWS)

  • WRC 376:1992 Metal Fatigue In Operating Nuclear Power Plants

IAEA - International Atomic Energy Agency

SCC

Institute of Electrical and Electronics Engineers (IEEE)

  • IEEE 323-1983 Qualifying class 1E equipment for nuclear power generating stations
  • IEEE 323-2003 Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
  • IEEE 603-2009 Standard criteria for safety systems for nuclear power generating stations
  • IEEE 603-1998 Criteria for safety systems for nuclear power generating stations
  • IEEE 603-1980 Criteria for safety systems for nuclear power generating stations
  • IEEE Std 765-1983 IEEE Standard for Preferred Power Supply for Nuclear Power Generating Stations
  • IEEE 603/COR-2015 Standard Criteria for Safety Systems for Nuclear Power Generating Stations
  • IEEE Std 765-1995 IEEE Standard for preferred power supply(PPS) for nuclear power generating stations
  • IEEE Std 765-2006 Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
  • IEEE 765-1983 IEEE Standard for Preferred Power Supply for Nuclear Power Generating Stations
  • IEEE 308-2001 Criteria for class 1E power systems for nuclear power generating stations
  • IEEE Std 603-1998 IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
  • IEEE 308-1991 Criteria for class 1E power systems for nuclear power generating stations
  • IEEE Std 765-2002 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations
  • IEEE 334-1994 Qualifying continuous duty class 1E motors for nuclear power generating stations
  • IEEE 638-2013 Qualification of Class 1E Transformers for Nuclear Power Generating Stations
  • IEEE Std 308-2001 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE Std 308-2020 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE 765-2022 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
  • IEEE 638-1992 Qualification of Class 1E Transformers for Nuclear Power Generating Stations
  • IEEE Unapproved Draft Std P692/D3c, Oct 2009 Draft Standard Criteria for Security Systems for Nuclear Power Generating Stations
  • IEEE 382-1985 Qualification of actuators for power operated valve assemblies with safety-related functions for nuclear power plants
  • IEEE Std 308-2012 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE Std 765-2012 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
  • IEEE 383-2015 Qualifying Electric Cables and Splices for Nuclear Facilities
  • IEEE 308-2020 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE Std 765-2022 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
  • IEEE Std 308-1991 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE 308-2012 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE 308-1970 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
  • IEEE No 308-1970 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations

HU-MSZT

  • MSZ 14345/3-1980 Nuclear energy, nuclear energy, basic concepts of nuclear power plants

International Organization for Standardization (ISO)

SE-SIS

Korean Agency for Technology and Standards (KATS)

American Nuclear Society (ANS)

  • ANS 2.2-2002 Earthquake Instrumentation Criteria for Nuclear Power Plants
  • ANS 2.23-2016 Nuclear Power Plant Response to an Earthquake
  • ANS 2.23-2002 Nuclear Plant Response to an Earthquake
  • ANS 6.4-1997 Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants

Danish Standards Foundation

European Committee for Electrotechnical Standardization(CENELEC)

JP-JEM

Canadian Standards Association (CSA)

  • CSA N293-2012 Fire protection for nuclear power plants (Fourth Edition)
  • CSA N293-07-2008 Fire Protection in CANDU Nuclear Power Plants Third Edition
  • CSA N293-07-2007 Fire protection for CANDU nuclear power plants Third Edition; Reprinted January 2008; Incorporates Update No 1: January 2008; Supplement No 1: November 2008; Update No 2: July 2009; Supplement No 2: January 2010

GSO

International Electrotechnical Commission (IEC)

  • IEC 60964:2009 Nuclear power plants - Control rooms - Design
  • IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations

ES-UNE

  • UNE-EN IEC 60964:2019 Nuclear power plants - Control rooms - Design (Endorsed by Asociación Española de Normalización in August of 2019.)

Association Francaise de Normalisation

VE-FONDONORMA

IEEE - The Institute of Electrical and Electronics Engineers@ Inc.

  • IEEE 765-1995 Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations
  • IEEE 765-2002 Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations
  • IEEE N42.7-1972 Criteria for Protection Systems for Nuclear Power Generating Stations
  • IEEE 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations
  • IEEE 308-1971 Criteria for Class IE Electric Systems for Nuclear Power Generating Stations
  • IEEE 535 INT 1-2009 Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations
  • IEEE 692-2013 Standard Criteria for Security Systems for Nuclear Power Generating Stations
  • IEEE 323-1974 Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
  • IEEE 603 ERTA-2015 Standard Criteria for Safety Systems for Nuclear Power Generating Stations
  • IEEE 535-1979 QUALIFICATION OF CLASS 1E LEAD STORAGE BATTERIES FOR NUCLEAR POWER GENERATING STATIONS
  • IEEE 638 ERTA-1999 Qualification of Class 1E Transformers for Nuclear Power Generating Stations
  • IEEE 692-1997 Standard Criteria for Security Systems for Nuclear Power Generating Stations
  • IEEE 692-2010 Standard Criteria for Security Systems for Nuclear Power Generating Stations

ANS - American Nuclear Society

  • 54.1-1989 General Safety Design Criteria for a Liquid Metal Reactor Nuclear Power Plant
  • 58.4-1979 CRITERIA FOR TECHNICAL SPECIFICATIONS FOR NUCLEAR POWER STATIONS
  • 2.23-2002 Nuclear Plant Response to an Earthquake
  • 2.23-2016 Nuclear Power Plant Response to an Earthquake
  • 2.13-1979 Evaluation of Surface-Water Supplies for Nuclear Power Sites
  • 6.4-1997 Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants
  • 6.4-2006 Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants
  • 2.17-2010 evaluation of subsurface radionuclide transport at commercial nuclear power plants

British Standards Institution (BSI)

  • ASME OM-2022 Operation and Maintenance of Nuclear Power Plants
  • BS ISO 4917-4:2024 Design of nuclear power plants against seismic events - Components
  • BS ISO 23467:2020 Ice plug isolation of piping in nuclear power plant
  • BS ISO 4917-6:2024 Design of nuclear power plants against seismic events - Post-seismic measures
  • BS IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations

American National Standards Institute (ANSI)

IT-UNI

American Society of Mechanical Engineers (ASME)

  • ASME S0003R-2001 Section III: Rules for Construction of Nuclear Power Plant Components Subsection NCA
  • ASME S0003R ADDENDA-2002 Section III: Rules for Construction of Nuclear Power Plant Components Subsection NCA
  • ASME S0003R ADDENDA-2001 Section III: Rules for Construction of Nuclear Power Plant Components Subsection NCA
  • ASME OM-1990 Code for operation and maintenance of nuclear power plants
  • ASME OM-1995 Code for operation and maintenance of nuclear power plants
  • ASME OM-2001 Code for the Operation and Maintenance of Nuclear Power Plants with Addenda (OM - 2001)

PL-PKN

  • PN O91061-1992 Protective footwear. Footwear for atomic plant workers

German Institute for Standardization

Lithuanian Standards Office

RU-GOST R

  • GOST 31901-2013 Pipeline valves for nuclear stations. General specifications

BELST

  • STB 2334-2013 Nuclear power plants. Safety. Protection of nuclear power plant`s computer systems. General requirements