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anti nuclear

anti nuclear, Total:266 items.

In the international standard classification, anti nuclear involves: Nuclear energy engineering, Vocabularies, Iron and steel products, Radiation measurements, Quantities and units, Graphical symbols, Air quality, Accident and disaster control, Protection of and in buildings, Rubber and plastics products, Test conditions and procedures in general, Physics. Chemistry, Radiation protection, Testing of metals, Applications of information technology, Wastes, Acoustics and acoustic measurements, Pipeline components and pipelines, Protection against fire, Packaging and distribution of goods in general, Microbiology, Milk and milk products, Corrosion of metals, Materials for aerospace construction, Plastics, Coals.

SE-SIS, anti nuclear

SIS SS IEC 639:1981 Nuclear instrumentation - Nuclear reactors - Use of the protection system for non-safety purposes
SIS SS 01 61 82-1979 Quantities and units — Nuclear reactions and ionizing radiations
SIS SS-ISO 10 645:1992 Nuclear energy — Light water reactors — Calculation of the decay heat power in nuclear fuels
SIS SS IEC 232:1983 Nuclear instrumentation - General characteristics of nuclear reactor instrumentation
SIS SS IEC 231:1983 Nuclear instrumentation - General principles of nuclear reactor instrumentation
SIS SS IEC 671:1983 Nuclear instrumentation - Protection system of nuclear reactors - Period/c tests and monitoring

American Society of Mechanical Engineers (ASME), anti nuclear

ASME N-7-2010 Nuclear Containments
ASME N-7-2002 Nuclear Containments Data Report (07/01)
ASME STP-NU-009-2008 Graphite for High Temperature Gas-Cooled Nuclear Reactors
ASME N-1-2011 Certificate Holders' Data Report For Nuclear Vessels
ASME RA-S-1.4-2021 Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants
ASME PTC 32.2 Report-1978 Methods of measuring the performance of nuclear reactor fuel in light water reactors

British Standards Institution (BSI), anti nuclear

BS ISO 4233:2023 Reactor technology. Nuclear fusion reactors. Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
BS ISO 12749-5:2018 Nuclear energy, nuclear technologies, and radiological protection. Vocabulary - Nuclear reactors
BS ISO 2889:2010 Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities
BS 4877:1972 Recommendations for general principles of nuclear reactor instrumentation
BS ISO 10645:2022 Nuclear energy. Light water reactors. Decay heat power in non-recycled nuclear fuels
BS 4877:2016 Tracked Changes. Nuclear reactor instrumentation and control. Code of practice
BS 6078:1981 Guide to the application of digital computers to nuclear reactor instrumentation and control
21/30381261 DC BS ISO 10645. Nuclear energy. Light water reactors. Decay heat power in non-recycled nuclear fuels
BS IEC 61501:1998 Nuclear reactor instrumentation. Wide range neutron fluence rate meter. Mean square voltage method
BS ISO 26802:2010 Nuclear facilities. Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
BS IEC 61501:2001 Nuclear reactor instrumentation - Wide range neutron fluence rate meter - Mean square voltage method
BS EN ISO 18229:2021 Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors
BS IEC 62117:2000 Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown

HU-MSZT, anti nuclear

Professional Standard - Nuclear Industry, anti nuclear

EJ/T 567-1991 Nuclear Reactor Instrumentation Terminology
EJ/T 444-1989 Regulations on Nuclear Design Contents of 300MW Pressurized Water Reactor Nuclear Power Plant
EJ/T 20032-2012 Design criteria for beryllium reflectors for space thermionic reactor nuclear power plants
EJ/T 20034-2012 Nuclear design criteria for space thermionic reactor nuclear power plant
EJ/T 1014-2005 Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors
EJ/T 959-1995 Data Processing Method for Thermal Neutron Flux Measurement in Nuclear Reactor
EJ/T 20050-2014 Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
EJ/T 318-1992 Reactor Design Criteria for Pressurized Water Reactor Nuclear Power Plants
EJ/T 20033-2012 Thermal Fluid Dynamics Design Criteria for Space Thermionic Reactor Nuclear Power Plant
EJ/T 1113-2000 Initial critical test in PWR nuclear power plant
EJ/T 1114-2000 Initial loading test for PWR nuclear power plant
EJ/T 320-1998 General design criteria of reactor for pressurized water reactor nuclear power plants
EJ/T 20132-2016 Design criterion for thermionic fuel elements of space nuclear power system with thermionic reactor

Korean Agency for Technology and Standards (KATS), anti nuclear

KS A ISO 17873-2012(2017) Nuclear facilities－Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
KS C IEC 60231D:2012 Fourth supplement:Principles of instrumentation for pressurized water reactors
KS C IEC 60557:2004 IEC terminology in the nuclear reactor field
KS C IEC 60231:2012 General principles of nuclear reactor instrumentation
KS D 3748-2008(2018) Steel for steam evaporator of nuclear reactor
KS A ISO 10645:2006 Nuclear energy－Light water reactors－Calculation of the decay heat power in nuclear fuels
KS A ISO 10645-2006(2021) Nuclear energy－Light water reactors－Calculation of the decay heat power in nuclear fuels
KS D 3748-2008 Steel for steam evaporator of nuclear reactor
KS D 3748-1993 Steel for steam evaporator of nuclear reactor
KS C IEC 60231-2012(2017) General principles of nuclear reactor instrumentation
KS C IEC 60231-2012(2022) General principles of nuclear reactor instrumentation
KS A ISO 17873-2012(2022) Nuclear facilities－Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
KS C IEC 60231A:2012 General principal of nuclear reactor instrumentation－First supplement to publication 60231(1967)
KS A ISO 17873:2012 Nuclear facilities-Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
KS C IEC 60671:2012 Nuclear power plants-Instrumentation and control systems important to safety-Surveillance testing
KS A ISO 31-10-2001(2006) Quantities and units－Part 10：Nuclear reactions and ionizing radiations
KS C IEC 61224:2012 Nuclear reactors－Response time in resistance temperature detectors(RTD)－In situ measurements
KS A ISO 31-10:2012 Quantities and units－Part 10：Nuclear reactions and ionizing radiations
KS C IEC 61224-2012(2022) Nuclear reactors－Response time in resistance temperature detectors(RTD)－In situ measurements
KS C IEC 61224-2012(2017) Nuclear reactors－Response time in resistance temperature detectors(RTD)－In situ measurements
KS C IEC 60231A-2012(2017) General principal of nuclear reactor instrumentation－First supplement to publication 60231(1967)
KS A ISO 10979-2012(2022) Identification of fuel assemblies for nuclear power reactors
KS C IEC 60231A-2012(2022) General principal of nuclear reactor instrumentation－First supplement to publication 60231(1967)
KS C IEC 60911-2004(2019) Measurements for monitoring adequate cooling within the core of pressurized light water reactors
KS C IEC 61250-2006(2016) Nuclear reactors－Instrumentation and control systems important for safety－Detection of leakage in coolant systems
KS C IEC 62117:2009 Nuclear reactor instrumentation- Pressurized light water reactors(PWR)- Monitoring adequate cooling within the core during cold shutdown

Indonesia Standards, anti nuclear

SNI 18-2034-1990 Nuclear reactor site, Guide for determination
SNI IEC 60557:2009 IEC Terminology in nuclear reactor field
SNI 18-4149-1996 Personnel qualification for operation and maintenance of nuclear reactor

RU-GOST R, anti nuclear

GOST 23082-1978 Nuclear reactors. Terms and definitions
GOST R 51964-2002 Transport packages of nuclear reactors spent fuel. Types and basic parameters
GOST 28506-1990 Fuel assemblies in nuclear power WWER reactors. Fuel failure detection methods
GOST 17137-1987 Monitoring, control and protection systems of nuclear reactors. Terms and definitions
GOST 26013-1983 Packing transport sets for used fuel assemblies from nuclear reactors. General technical requirements
GOST 26843-1986 Nuclear power reactors. General requirements for control and testify systems
GOST R 25645.332-1994 Polimeric materials for spacecrafts with nuclear reactor. Requiremens to radiation tests
GOST 27445-1987 Neutron flux monitoring systems for control and protection of nuclear reactors. General technical requirements

US-FCR, anti nuclear

FCR DOE 5480.6-1986 SAFETY OF DEPARTMENT OF ENERGY-OWNED NUCLEAR REACTORS
FCR DOE 5480.30-1993 NUCLEAR REACTOR SAFETY DESIGN CRITERIA
FCR NE-F-6-2T-1973 WELDING OF REACTOR CORE COMPONENTS AND TEST ASSEMBLIES
FCR NE-F-3-10T (1)-1979 NONDESTRUCTIVE EXAMINATION OF REACTOR CORE COMPONENTS (INACTIVE FOR NEW DESIGN)
FCR NE-F-3-10T-1977 NONDESTRUCTIVE EXAMINATION OF REACTOR CORE COMPONENTS (INACTIVE FOR NEW DESIGN)
FCR NE-F-3-10T (2)-1980 NONDESTRUCTIVE EXAMINATION OF REACTOR CORE COMPONENTS (INACTIVE FOR NEW DESIGN)
FCR DOE-STD-101-92-1992 COMPILATION OF NUCLEAR SAFETY CRITERIA FOR POTENTIAL APPLICATION TO DOE NONREACTOR NUCLEAR FACILITIES

RO-ASRO, anti nuclear

STAS 6729/2-1984 Nuclear energv NUCLEAR REACTOR TECHNOLOGY Glossary
SR ISO 31-10:1995 Quantities and units - Part 10: Nuclear reactions and ionizing radiations
STAS 6729/1-1982 Nuclear energy PHYSICS OF NUCLEAR REACTORS Glosaary
STAS 12912-1990 Radiation detectors for the instrumentation and protection of nuclear reactors. Characteristics and test methods
STAS 737/15-1983 International system of units (SI) UNITS CHARAGTERISTICS QUAN- TITIES OF NUCLEAR REACTIONS AND IONIZING RADIATIONS

TR-TSE, anti nuclear

TS 2596-1977 General Characteristics of Nuclear Reactor Instn?mentation
TS 1827-1975 QUANTITIES AND UNITS OF NUCLEAR REACTIONS AND IONIZING RADIATIONS
TS 3603-1981 RADIATION DETECTORS FOR THE INSTRUMENTATION AND PROTECTION OF NUCLEAR REACTORS

International Electrotechnical Commission (IEC), anti nuclear

IEC 60231:1967 General principles of nuclear reactor instrumentation
IEC 60557:1982 I E C terminology in the nuclear reactor field
IEC 60232:1966 General characteristics of nuclear reactor instrumentation
IEC 60231A:1969 General principles of nuclear reactor instrumentation
IEC TR 61510:1996 RBMK nuclear reactors - Proposals for instrumentation and control improvements
IEC 61505:1998 Nuclear reactor instrumentation - Boiling water reactors (BWR) - Stability monitoring
IEC TR3 61510:1996 RBMK nuclear reactors - Proposals for instrumentation and control improvements
IEC 60639:1979 Nuclear reactors. Use of the protection system for non-safety purposes
IEC 60671:1980 Periodic tests and monitoring of the protection system of nuclear reactors
IEC 60231D:1975 General principles of nuclear reactor instrumentation
IEC 61501:1998 Nuclear reactor instrumentation - Wide range neutron fluence rate meter - Mean square voltage method
IEC 61224:1993 Nuclear reactors; response time in resistance temperature detectors (RTD); in situ measurements
IEC 60643:1979 Application of digital computers to nuclear reactor instrumentation and control
IEC 60231G:1977 General principles of nuclear reactor instrumentation. Seventh supplement: Liquid-metal cooled fast reactor
IEC 61343:1996 Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core
IEC 60231B:1972 General principles of nuclear reactor instrumentation
IEC 60231C:1974 General principles of nuclear reactor instrumentation
IEC 60231F:1977 General principles of nuclear reactor instrumentation. Sixth supplement: Heavy-water-moderated reactor with steam generating direct-cycle turbine

CZ-CSN, anti nuclear

CSN IEC 231:1994 General principles of nuclear reactor instrumentation
CSN IEC 639:1994 Nuclear reactors.Use of the protection system for non-safety purposes
CSN IEC 643:1994 Application of digital computers to nuclear reactor instrumentation and control
CSN 35 6580-1987 Monitoring, control and protection systems of nuclear reactors. erms and definitions

International Organization for Standardization (ISO), anti nuclear

ISO 10645:1992 Nuclear energy; light water reactors; calculation of the decay heat power in nuclear fuels
ISO 4233:2023 Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
ISO 31-10:1973 Title missing - Legacy paper document
ISO 31-10:1980 Quantities and units of nuclear reactions and ionizing radiations
ISO 17873:2004 Nuclear facilities - Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
ISO 31-10:1992 Quantities and units; part 10: nuclear reactions and ionizing radiations
ISO 12749-5:2018 Nuclear energy, nuclear technologies, and radiological protection - Vocabulary - Part 5: Nuclear reactors
ISO 10645:2022 Nuclear energy — Light water reactors — Decay heat power in non-recycled nuclear fuels
ISO 31-10:1980/Amd 1:1985 Quantities and units of nuclear reactions and ionizing radiations — Amendment 1
ISO 31-10:1992/Amd 1:1998 Quantities and units - Part 10: Nuclear reactions and ionizing radiations; Amendment 1
ISO 26802:2010 Nuclear facilities - Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
ISO 10979:1994 Identification of fuel assemblies for nuclear power reactors
ISO/CD 3579 Reactor technology — Nuclear Power Plants —Installation of Structural modules
ISO 18229:2018 Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

KR-KS, anti nuclear

KS D 3748-2008(2023) Steel for steam evaporator of nuclear reactor

American Nuclear Society (ANS), anti nuclear

ANS 19.3.4-2002 The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
ANS 5.10-1998 Airborne Release Fractions at Non-Reactor Nuclear Facilities (Includes Appendix A: 2013, Appendix B and Appendix C)
ANS 19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
ANS 58.16-2014 Safety Categorization and Design Criteria for Nonreactor Nuclear Facilities
ANS 55.6-1993 Liquid Radioactive Waste Processing System for Light Water Reactor Plants
ANS RA-S-1.4-2021 Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants

General Administration of Quality Supervision, Inspection and Quarantine of the People‘s Republic of China, anti nuclear

GB/T 4083-1983 General safety principles of nuclear reactor protection system
GB/T 4083-2005 General safety principles of nuclear reactor protection system
GB 3102.10-1993 Quantities and units of nuclear reactions and ionizing radiations
GB/T 8995-1988 In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB/T 8995-2008 In-core instrumentation for neutron fluence rate measurements in nuclear reactors
GB 12789.2-1991 Nuclear Reactor Instrumentation Guidelines Part II: Pressurized Water Reactors
GB/T 12789.2-1991 Criteria for nuclear reactor instrumentation--Part 2: Pressurized water reactors
GB/T 13368-1992 Specifiation of nuclear fuel rods for miniature neutron source reactor
GB/T 13368-2008 Specification for nuclear fuel rods of miniature neutron source reactor
GB 12789.1-1991 Guidelines for Nuclear Reactor Instrumentation Part I: General Principles
GB/T 12789.1-1991 Criteria for nuclear reactor instrumentation--Part 1: General principes
GB/T 12789.3-1992 Criteria for nuclear reactor reactor instrumentation Part three. High temperature gas-cooled reactor(HTGR)
GB 12789.3-1992 Nuclear Reactor Instrumentation Guidelines Part III: High Temperature Gas Cooled Reactors
GB/T 13628-1992 Nuclear reactor use of the protection system for non-safety purpose
GB/T 5203-2011 Safety logic assemblies of nuclear reactor characteristics and test methods
GB/T 5203-1985 Safety logic assemblies of nuclear reactor characteristics and test methods
GB/T 7164-1994 Radiation detectors for nuclear reactors. Characteristics and test methods
GB/T 7164-2004 Radiation detectors for nuclear reactors Characteristics and test methods
GB/T 12789.4-1994 Criteria for nuclear reactor instrumentation. Part four: Liquid-metal cooled fast reactors
GB/T 12789.4-94 Nuclear Reactor Instrumentation Guidelines Part IV: Liquid Metal Cooled Fast Reactors
GB/T 41591-2022 Initial criticality tests for pressurized water reactor of nuclear power plants

Group Standards of the People's Republic of China, anti nuclear

T/CECPA 003-2021 Validation Method for Reactor Nuclear Design Software
T/CSTM 00915-2023 Powder-packed box-type thermal insulation products for nuclear reactors
T/TLRIA 0005-2018 Rubber gaskets for ventilation systems in nuclear reactor pits
T/TLRIA 0004-2018 O - rings for coolant pump of nuclear reactor

American National Standards Institute （ANSI), anti nuclear

ANSI/ANS 19.3.4-2002 Determination of Thermal Energy Deposition Rates in Nuclear Reactors
ANSI/ANS 5.10-1998 Airborne Release Fractions at Non-Reactor Nuclear Facilities
ANSI/ANS 56.8-2002 Nuclear Reactors – Containment System Leakage Testing Requirements
ANSI/ANS 2.23-2002 Nuclear Plant Response to an Earthquake
ANSI/ANS RA-S-1.4-2021 Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants
ANSI/NFPA 806-2010 Performance Based Standard for Fire Protection for Advanced Nuclear Reactor Electric Generating Plants Change Process

Taiwan Provincial Standard of the People's Republic of China, anti nuclear

CNS 11296-10-1985 Quantities and Units of Nuclear Reactions and Ionizing Radiations
CNS 11296.10-1985 Quantities and Units of Nuclear Reactions and Ionizing Radiations

国家技术监督局, anti nuclear

GB/T 3102.10-1993 Quantities and units of nuclear reactions and ionizing radiations

German Institute for Standardization, anti nuclear

DIN 25411:1991 Nuclear reactors; graphical symbols and short forms
DIN 25433:2016-10 Fuel assembly identification for nuclear power reactors
DIN 25463-1:2014-02 Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors
DIN 25463-1:2014 Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors
DIN 25476:1987 Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25476:2012 Primary-coolant clean-up system in nuclear power plants with light water reactors
DIN 25463-2:2014 Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors
DIN 25463-1:1990 Decay heat power in nuclear fuels of light water reactors; non-recycled nuclear fuels
DIN 25433:1988 Fuel assembly identification for nuclear power reactors
DIN 25433:2016 Fuel assembly identification for nuclear power reactors
DIN 10197:1988 Microbiological analysis of milk; detection of staphylococcal thermonuclease; reference method

ANS - American Nuclear Society, anti nuclear

19.3.4-2002 The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
19.3.4-1976 Determination of Thermal Energy Deposition Rates in Nuclear Reactors
5.10-1998 Airborne Release Fractions at Non-Reactor Nuclear Facilities
19.3-1983 DETERMINATION OF NEUTRON REACTION RATE DISTRIBUTIONS AND REACTIVITY OF NUCLEAR REACTORS
N45.4-1972 Leakage-rate testing of containment structures for nuclear reactors
19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
58.16-2014 Safety Categorization and Design Criteria for Nonreactor Nuclear Facilities
54.1-1989 General Safety Design Criteria for a Liquid Metal Reactor Nuclear Power Plant
6.8.1-1981 LOCATION AND DESIGN CRITERIA FOR AREA RADIATION MONITORING SYSTEMS FOR LIGHT WATER NUCLEAR REACTORS

U.S. Military Regulations and Norms, anti nuclear

ARMY MIL-DTL-3628/34 K VALID NOTICE 3-2013 Badge, Qualification, Nuclear Reactor Operators, Army
ARMY MIL-E-63300 A NOTICE 1-1997 ELECTRONIC ASSEMBLY FOR MINE, ANTIPERSONNEL, HE, M74
ARMY MIL-E-63300 A (4)-1986 ELECTRONIC ASSEMBLY FOR MINE, ANTIPERSONNEL, HE, M74
ARMY MIL-E-63300 A-1981 ELECTRONIC ASSEMBLY FOR MINE, ANTIPERSONNEL, HE, M74
ARMY MIL-E-63399 B NOTICE 1-1997 ELECTRONICS-MCD ASSEMBLY FOR MINE, ANTITANK: HE, M75
ARMY MIL-E-63399 B (7)-1990 ELECTRONICS-MCD ASSEMBLY FOR MINE, ANTITANK: HE, M75
ARMY MIL-E-63399 B-1981 ELECTRONICS-MCD ASSEMBLY FOR MINE, ANTITANK: HE, M75

Association Francaise de Normalisation, anti nuclear

NF ISO 17873:2006 Installations nucléaires - Critères pour la conception et l'exploitation des systèmes de ventilation des installations nucléaires autres que les réacteurs nucléaires
NF M62-250*NF ISO 17873:2006 Nuclear facilities - Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors.
NF ISO 26802:2010 Installations nucléaires - Critères pour la conception et l'exploitation des systèmes de confinement et de ventilation des réacteurs nucléaires
NF M62-251*NF ISO 26802:2010 Nuclear facilities - Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
NF M64-002*NF EN ISO 18229:2021 Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors
NF EN ISO 18229:2021 Exigences techniques essentielles pour les composants mécaniques et les structures métalliques destinés aux réacteurs nucléaires de quatrième génération

Danish Standards Foundation, anti nuclear

DS/ISO 31/10:1984 Quantities and units of nuclear reactions and ionizing radiations

BE-NBN, anti nuclear

NBN X 02-110-1990 Quantifies and unit s of nuclear reactions and ionizing radiations

Military Standard of the People's Republic of China-Commission of Science,Technology and Industry for National Defence, anti nuclear

GJB 5405-2005 Glossary of term:space nuclear power system with thermionic reactor

Professional Standard - Energy, anti nuclear

NB/T 20102-2012 Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors
NB/T 20144-2012 Initial criticality tests for pressurized water reactor of nuclear power plants
NB/T 20434-2017RK PWR Nuclear Power Plant Reactor's First Fuel Loading Test

American Society for Testing and Materials (ASTM), anti nuclear

ASTM E185-73 Standard Recommended Practice for Surveillance Tests For Nuclear Reactor Vessels
ASTM E50-90(1995)e1 Standard Practice for Apparatus, Reagents, and safety Precautions for Chemical Analysis of Metals
ASTM E509/E509M-21 Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
ASTM E50-11(2016) Standard Practices for Apparatus, Reagents, and Safety Considerations for Chemical Analysis of Metals, Ores, and Related Materials
ASTM E509-97 Standard Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor Vessels
ASTM E185-16 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E509/E509M-14 Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
ASTM B811-13(2022)e1 Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM C781-19 Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
ASTM B811-02(2007) Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM B811-02 Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM B811-01 Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM B811-97 Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM C781-18 Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
ASTM C781-20 Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
ASTM B811-13e1 Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM B811-13(2017) Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM B811-13 Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding
ASTM E636-14e1 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
ASTM E636-20 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels
ASTM E509-03 Standard Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor Vessels
ASTM E1035-85(1996) Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
ASTM E1035-85(1990) Standard Practice for Determining Radiation Exposures for Nuclear Reactor Vessel Support Structures
ASTM E1035-13 Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
ASTM E509-03(2008) Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels
ASTM E185-02 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM D6347/D6347M-05 Standard Test Method for Determination of Bulk Density of Coal Using Nuclear Backscatter Depth Density Methods
ASTM E185-15e1 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E1035-18(2023) Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
ASTM E1035-18 Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
ASTM E1035-02 Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures
ASTM E1035-08 Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures

Japanese Industrial Standards Committee (JISC), anti nuclear

JIS Z 8202-10:2000 Quantities and units -- Part 10: Nuclear reactions and ionizing radiations

IAEA - International Atomic Energy Agency, anti nuclear

NS-G-1.12-2005 Design of the Reactor Core for Nuclear Power Plants
NS-G-1.10-2004 Design of Reactor Containment Systems for Nuclear Power Plants

Military Standard of the People's Republic of China-General Armament Department, anti nuclear

GJB 4256-2001 Safety requirements for external nuclear criticality of nuclear submarine reactor fuel elements
GJB 843.18-1994 Safety regulations for submarine nuclear power plant design Nuclear design criteria for pressurized water reactors

IT-UNI, anti nuclear

PL-PKN, anti nuclear

PN J01101-1989 Nuclear technics Inspection, control and protection systems of nuclear reactor Terms and definitions

IN-BIS, anti nuclear

IS 1890 Pt.10-1983

国家市场监督管理总局、中国国家标准化管理委员会, anti nuclear

GB/T 7164-2022 Characteristics and test methods of radiation detectors for nuclear reactors
GB/T 37623-2019 Corrosion of metals and alloys—Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors

Professional Standard - Electricity, anti nuclear

DL/T 1142-2009 Software test for reactor control system of nuclear power plants

Professional Standard - Medicine, anti nuclear

YY/T 1303-2015 Nucleic acid amplification reverse dot blot reagent(kit)

European Committee for Standardization (CEN), anti nuclear

EN ISO 18229:2021 Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018)

AT-ON, anti nuclear

ONORM DIN 10197-1994 Microbiological analysis of milk. Detection of staphylococcal thermonuclease. Reference method

ES-UNE, anti nuclear

UNE-EN ISO 18229:2021 Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors (ISO 18229:2018) (Endorsed by Asociación Española de Normalización in September of 2021.)

未注明发布机构, anti nuclear

BS ISO 18229:2018 Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors

Professional Standard-Ships, anti nuclear

CB 20141-2014 Sealing technology for end of cable in nuclear submarin reactor cabins

Canadian Standards Association (CSA), anti nuclear

CSA N290.4-2011 Requirements for reactor control systems of nuclear power plants (Second Edition)
CSA N291-08-2008 Requirements for safety-related structures for CANDU nuclear power plants First Edition

国家能源局, anti nuclear

NB/T 20434-2017 First charging test of pressurized water reactor nuclear power plant reactor

WRC - Welding Research Council, anti nuclear

BULLETIN 382-1993 NUCLEAR PIPING CRITERIA FOR ADVANCED LIGHT-WATER REACTORS@ VOLUME 1?FAILURE MECHANISMS AND CORRECTIVE ACTIONS

American Welding Society (AWS), anti nuclear

WRC 382:1993 Nuclear Piping Criteria for Advanced Light-Water Reactors Volume 1 - Failure Mechanisms and Corrective Actions