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
- GB/T 36163-2018 Alloy steel plate for nuclear power plants
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
- DB36/T 479-2005 Phnom Penh Daphne
- DB36/T 507-2006 Phnom Penh daphne seedlings
- DB36/T 508-2006 Phnom Penh Daphne Transportation
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
- T/JSQA 175-2023 Measurement cables for nuclear power fenerating stations
- T/ZZB 007-2015 Centrifugal fans for nuclear island of nuclear power plant
- T/ZZB 0099-2016 Axial fans for nuclear island of nuclear power plant
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
- DB62/T 4385-2021 Jinruibao melon variety
- DB62/T 4389-2021 Watermelon Variety Jinrui No.1
- DB62/T 4390-2021 Watermelon Variety Jinrui No.5
American Welding Society (AWS)
- WRC 376:1992 Metal Fatigue In Operating Nuclear Power Plants
IAEA - International Atomic Energy Agency
- SSG-28-2014 Commissioning for Nuclear Power Plants
- NS-G-2.9-2003 Commissioning for Nuclear Power Plants
- NS-G-2.3-2001 Modifications to Nuclear Power Plants
- NS-R-1-2004 Safety of Nuclear Power Plants: Design
- SSG-13-2011 Chemistry Programme for Water Cooled Nuclear Power Plants
- NS-G-1.8-2004 Design of Emergency Power Systems for Nuclear Power Plants
- NS-G-1.12-2005 Design of the Reactor Core for Nuclear Power Plants
SCC
- ANS 3.3-1982 Security for Nuclear Power Plants
- ANS 3.3-1988 Security for Nuclear Power Plants
- CAN/CSA-N293-1995(R2006) Fire Protection for CANDU Nuclear Power Plants
- UNE 73102:1992 MANAGEMENT OF NUCLEAR POWER PLANTS STARTUP.
- CAN/CSA-N293-M87-1987 Fire Protection for CANDU Nuclear Power Plants
- CSA N293-2007(R2012) Fire protection for CANDU nuclear power plants
- CAN/CSA N293-1995(R2001) Fire Protection for CANDU Nuclear Power Plants
- DANSK DS/EN 60964:2010 Nuclear power plants – Control rooms – Design
- CEI EN IEC 60964:2020 Nuclear power plants - Control rooms - Design
- DANSK DS/EN IEC 60964:2019 Nuclear power plants – Control rooms – Design
- DANSK DS/EN IEC 60964/AC:2019 Nuclear power plants – Control rooms – Design
- CEI EN 60964:2011 Nuclear power plants - Control rooms - Design
- CSA N290.8-15:2016 Technical specifications for nuclear power plant components
- CAN3-N286.3-1983 Construction quality assurance of nuclear power plants
- CSA N290.17-2023 Probabilistic safety assessment for nuclear power plants
- CAN3-N286.2-1986 Quality assurance of nuclear power plant design
- ANS 58.4-1979 Criteria for Technical Specifications for Nuclear Power Stations
- ASME OM-2017 Operation and Maintenance of Nuclear Power Plants
- ANS 2.23-2002(W2016) Nuclear Plant Response to an Earthquake
- CSA N286.3-1999 Construction Quality Assurance for Nuclear Power Plants
- ANS 2.23-2016(R2020) Nuclear Plant Response to an Earthquake
- ANS 54.1-1989(W1999) General Safety Design Criteria for a Liquid Metal Reactor Nuclear Power Plant
- ANS 3.7.2-1979 Emergency Control Centers for Nuclear Power Plants
- CAN/CSA N286.6-1998 Decommissioning Quality Assurance for Nuclear Power Plants
- CEI EN IEC 63046:2022 Nuclear power plants - Electrical power system - General requirements
- CSA N285.4-2005 Periodic inspection of CANDU nuclear power plant components
- CAN/CSA-N285.4-1994(C2005) Periodic inspection of CANDU nuclear power plant components
- CSA N285.4-14:2014 Periodic inspection of CANDU nuclear power plant components
- BS PD IEC TR 63214:2019 Nuclear power plants. Control rooms. Human factors engineering
- CAN3 N290.1-1980(R2011) Requirements for the Shutdown Systems of CANDU Nuclear Power Plants
- CAN3-N290.1-1980(R2011) Requirements for the Shutdown Systems of CANDU Nuclear Power Plants
- ANS 2.13-1979(R1988) Evaluation of Surface-Water Supplies for Nuclear Power Sites
- CAN/CSA N289.5-M91-1991(R2008) Seismic Instrumentation Requirements for CANDU Nuclear Power Plants
- CAN/CSA-N289.5-M91-1991(R2008) Seismic Instrumentation Requirements for CANDU Nuclear Power Plants
- ANS 2.9-1980(R1989) Evaluation of Ground Water Supply for Nuclear Power Sites
- CAN/CSA-N289.5-M91-1991(C2008) Requirements for seismological systems in CANDU nuclear power plants
- CSA N290.13-2005(R2010) Environmental Qualification of Equipment for CANDU Nuclear Power Plants
- CAN 3-N285.4-M83-1983 Periodic inspection of CANDU nuclear power plant components
- CEI EN IEC 62855:2022 Nuclear power plants - Electrical power systems - Electrical power systems analysis
- CSA N285.4-2009 Periodic inspection of CANDU nuclear power plant components
- CAN/CSA-N290.5-M90-1990(R2006) Requirements for the Support Power Systems of CANDU Nuclear Power Plants
- CAN/CSA N290.5-M90-1990(R2001) Requirements for the Support Power Systems of CANDU Nuclear Power Plants
- DANSK DS/EN IEC 62855:2021 Nuclear power plants – Electrical power systems – Electrical power systems analysis
- ANS 54.1-2020 Nuclear Safety Criteria and Design Process for Sodium Fast Reactor Nuclear Power Plants
- ANS 2.17-1980(R1989) Evaluation of Radionuclide Transport in Ground Water for Nuclear Power Sites
- CSA N285.0-08/Série N285.6-2008 General Requirements for CANDU Nuclear Power Plant Pressure Systems and Components/CANDU Nuclear Power Plant Reactor Component Material Standards
- ANS 52.1-1978(W1983) Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants
- CSA N290.12-14:2015 Human factors in nuclear power plant design
- CSA N290.12-2023 Human factors in design for nuclear power plants
- CAN/CSA-N285.4-1994(R2005) Periodic Inspection of CANDU Nuclear Power Plant Components
- CSA N285.4-M1978-1978 Periodic Inspection of Candu Nuclear Power Plant Components
- 07/30135879 DC BS IEC 60964. Nuclear power plants. Control rooms. Design
- AENOR UNE 73107:1996 Fire protection in Nuclear Power Plants with light water reactors.
- ANS 2.5-1984 Standard for Determining Meteorological Information at Nuclear Power Sites
- ANS 3.1-1971 Selection and Training of Nuclear Power Plant Personnel
- CSA N285.4-2023 Periodic inspection of CANDU nuclear power plant components
- BS IEC 60780:1998 Nuclear power plants. Electrical equipment of the safety system. Qualification
- CSA N285.0-17/N285.6 Series-2017 General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants
- UNE 73107:1996 FIRE PROTECTION IN NPPS WITH LIGHT WATER REACTORS.
- ANS 3.7.3-1979 Radiological Emergency Preparedness Exercises for Nuclear Power Plants
- CAN/CSA N285.4-1994(R1999) Periodic Inspection of CANDU Nuclear Power Plant Components
- CSA N285.0-12/N285.6 Series-2012 General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants
- CSA N285.0-08/N285.6 Series-2008 General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants
- ANS 6.4-2006(R2021) Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants
- ANS 51.1-1983(R1988) Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants
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)
- ISO 4917-1:2024 Design of nuclear power plants against seismic events
- ISO 4917-3:2024 Design of nuclear power plants against seismic events
- ISO 4917-4:2024 Design of nuclear power plants against seismic events
- ISO/DIS 4917-5:2023 Design of Nuclear Power Plants against Seismic Events
- ISO/FDIS 4917-1:2023 Design of Nuclear Power Plants against Seismic Events
- ISO 4917-6:2024 Design of nuclear power plants against seismic events
- ISO/FDIS 4917-4:2023 Design of Nuclear Power Plants against Seismic Events
- ISO/FDIS 4917-3:2023 Design of Nuclear Power Plants against Seismic Events
- ISO/FDIS 4917-6:2023 Design of Nuclear Power Plants against Seismic Events
- ISO 23467:2020 Ice plug isolation of piping in nuclear power plant
SE-SIS
- SIS SS-ISO 6258:1988 Nuclear power plants — Design against seismic hazards
- SIS SS 436 90 02-1980 Nuclear power generating stations — Class IE electric systems
- SIS SS 01 66 01-1982 Swedish metal standards — Terminology
- SIS SS 01 66 01-1980 Swedish metal standards — Terminology
- SIS SS IEC 772:1986 Nuclear instrumentation - Electrical penetration assemblies in containment structures for nuclear power generating stations
- SIS SS IEC 880:1987 Nuclear instrumentation - Software for computers in the safety systems of nuclear power stations
Korean Agency for Technology and Standards (KATS)
- KS A ISO 6258-2006(2016) Nuclear power plants-Design against seismic hazards
- KS C IEC 60964-2022 Nuclear power plants-Control rooms-Design
- KS A ISO 8107-2021 Nuclear power plants-Maintainability-Terminology
- KS C IEC 61771-2012(2017) Nuclear power plants-Main control-room-Verification and validation of design
- KS C IEC 61227-2022 Nuclear power plants-Control rooms-Operator controls
- KS C IEC 60772:2012 Electrical penetration assemblies in containment structures for nuclear power generating stations
- KS C IEC 60951-5-2004(2014) Nuclear power plants-Radiation monitoring equipment for accident and post-accident conditions-Part 5:Radioactivity of air in light water nuclear power plants
- KS C IEC 61227-2012(2017) Nuclear power plants-Control rooms-Operator controls
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
- DS/EN 60964:2010 Nuclear power plants - Control rooms - Design
- DS/EN IEC 63046:2021 Nuclear power plants – Electrical power system – General requirements
- DS/EN IEC 62855:2021 Nuclear power plants – Electrical power systems – Electrical power systems analysis
European Committee for Electrotechnical Standardization(CENELEC)
- EN 60964:2010 Nuclear power plants - Control rooms - Design
- EN IEC 60964:2019 Nuclear power plants - Control rooms - Design
- EN IEC 62855:2021 Nuclear power plants - Electrical power systems - Electrical power systems analysis
- EN 61227:2016 Nuclear power plants - Control rooms - Operator controls
JP-JEM
- JEM 1423-2008 Inspection of nuclear power plant valves
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
- BH GSO IEC 60964:2016 Nuclear power plants - Control rooms - Design
- BH GSO ISO 8107:2017 Nuclear power plants -- Maintainability -- Terminology
- BH GSO IEC 62855:2022 Nuclear power plants - Electrical power systems - Electrical power systems analysis
- GSO IEC 62855:2021 Nuclear power plants - Electrical power systems - Electrical power systems analysis
- GSO IEC 63147:2021 Criteria for accident monitoring instrumentation for nuclear power generating stations
- BH GSO IEC 63147:2022 Criteria for accident monitoring instrumentation for nuclear power generating stations
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
- NF C19-204*NF EN 60964:2010 Nuclear power plants - Control rooms - Design
- NF C19-446*NF EN IEC 63046:2021 Nuclear power plants - Electrical power system - General requirements
- NF C19-455*NF EN IEC 62855:2021 Nuclear power plants - Electrical power systems - Electrical power systems analysis
- NF EN IEC 62855:2021 Nuclear power plants - Electric power systems - Analysis of electric power systems
- NF C19-227*NF EN 61227:2016 Nuclear power plants - Control rooms - Operator controls
VE-FONDONORMA
- NORVEN 387-1974 Venezuela Metal Electrolytic Coating Standard
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)
- ANSI/ANS 2.23-2016 Nuclear Power Plant Response to an Earthquake
- ANSI/IEEE 308:2001 Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
- ANSI/ANS 2.17-2010 Evaluation of Subsurface Radionuclide Transport at Commercial Nuclear Power Plants
- ANSI/ASME OM-2012 Operation and Maintenance of Nuclear Power Plants
IT-UNI
- UNI ISO 23467:2021 Ice plug isolation of piping in nuclear power plant
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
- DIN 25453:1991 Test program for shielding in nuclear power plants
- DIN 25453:2013 Test procedure for shielding in nuclear power plants
Lithuanian Standards Office
- LST EN 60964-2010 Nuclear power plants - Control rooms - Design (IEC 60964:2009)
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
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