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reaction
reaction, Total:233 items.
In the international standard classification, reaction involves: Non-ferrous metals, Nuclear energy engineering, Quantities and units, Character symbols, Physics. Chemistry, Equipment for the chemical industry, Equipment for petroleum and natural gas industries, Fluid storage devices, Plastics, Soil quality. Pedology, Radiation protection, Construction materials, Petroleum products in general, Accident and disaster control, Rubber, Testing of metals, Materials for aerospace construction, Transformers. Reactors, Radiation measurements, Reinforced plastics, Rubber and plastics products, Protection against fire, Iron and steel products, Corrosion of metals, Analytical chemistry, Thermodynamics and temperature measurements, Protection against dangerous goods, Ventilators. Fans. Air-conditioners, Photography.
General Administration of Quality Supervision, Inspection and Quarantine of the People‘s Republic of China, reaction
- GB/T 42656-2023 Test method for kinetic performance of hydrogen absorption and desorption reaction of rare earth hydrogen storage alloy
- GB/T 30098-2013 Laboratory magnetic driven autoclave
- GB/T 43062-2023 Determination of neutron fluence and atomic dislocation number (dpa) of nuclear energy reactor pressure vessels and internal components
American Society for Testing and Materials (ASTM), reaction
- ASTM E636-02 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
- ASTM E706-23 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
- ASTM E706-16 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
- ASTM E636-95 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
- ASTM E2956-14 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
- ASTM E2956-21 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
- ASTM E2956-23 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
- ASTM E706-02 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
- ASTM C1679-13 Standard Practice for Measuring Hydration Kinetics of Hydraulic Cementitious Mixtures Using Isothermal Calorimetry
- ASTM C1679-14 Standard Practice for Measuring Hydration Kinetics of Hydraulic Cementitious Mixtures Using Isothermal Calorimetry
- ASTM E482-07 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
- ASTM E482-11e1 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
- ASTM E2521-23 Standard Terminology for Evaluating Response Robot Capabilities
- ASTM E482-01 Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
- ASTM D3518/D3518M-94(2007) Standard Test Method for In-Plane Shear Response of Polymer Matrix Composite Materials by Tensile Test of a 177;45176; Laminate
- ASTM D3518/D3518M-13 Standard Test Method for In-Plane Shear Response of Polymer Matrix Composite Materials by Tensile Test of a plusmn;45deg; Laminate
- ASTM E1005-97 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
- ASTM E1005-15 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
- ASTM E1005-16 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
- ASTM E185-79 Standard Practice for Conducting Surveillance Tests For Light-Water Cooled Nuclear Power Reactor Vessels
- ASTM E2215-10 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM E1005-03e1 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
- ASTM E1005-03 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
- ASTM E636-95(2001) Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
- ASTM E636-09 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
- ASTM E636-14 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E?706 40;IH41;
- ASTM E185-10 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM E185-82e2 Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E 706 (IF)
- ASTM E636-10 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E 706 (IH)
- ASTM E185-21 Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM E3007-21 Standard Practice for Selection and Use of Kinetic Reference Values in the Study of Decomposition Reactions by Thermogravimetry
- ASTM E2853-12(2021) Standard Test Method for Evaluating Emergency Response Robot Capabilities: Human-System Interaction (HSI): Search Tasks: Random Mazes with Complex Terrain
- ASTM E2853/E2853M-22 Standard Test Method for Evaluating Ground Response Robot Capabilities: Search Tasks
- ASTM E2215-18 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM E2215-16 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM E2215-19 Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
- ASTM E706-01 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
- ASTM E706-87(1994) Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
- ASTM E706-23 Red Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards (Standard + Redline PDF Bundle)
- ASTM E3174-20 Standard Practice for Determination of Kinetic Reaction Model Using Differential Scanning Calorimetry
- ASTM E3174-21 Standard Practice for Determination of Kinetic Reaction Model Using Differential Scanning Calorimetry
- ASTM E3174-19 Standard Practice for Determination of Kinetic Reaction Model Using Differential Scanning Calorimetry
- ASTM E3174-22 Standard Practice for Determination of Kinetic Reaction Model Using Differential Scanning Calorimetry
- ASTM E3408/E3408M-23 Standard Test Method for Evaluating Ground Response Robot Capabilities: Dexterity: Linear Inspection
- ASTM E2245-05 Standard Test Method for Residual Strain Measurements of Thin, Reflecting Films Using an Optical Interferometer
- ASTM E2245-02 Standard Test Method for Residual Strain Measurements of Thin, Reflecting Films Using an Optical Interferometer
German Institute for Standardization, reaction
- DIN 13345:1978 Thermodynamics and kinetics of chemical reactions; symbols, units
- DIN 13345:1978-08 Thermodynamics and kinetics of chemical reactions; symbols, units
- DIN 25433:1988 Fuel assembly identification for nuclear power reactors
- DIN 25433:2016 Fuel assembly identification for nuclear power reactors
- DIN 53529-2:1983-03 Testing of rubber and elastomers; measurement of vulcanization characteristics (curometry); evaluation of cross-linking isotherms in terms of reaction kinetics
- DIN 53529-2:1983 Testing of rubber and elastomers; measurement of vulcanization characteristics (curometry); evaluation of cross-linking isotherms in terms of reaction kinetics
- DIN IEC 60568:2006 Nuclear power plants - Instrumentation important to safety - In-core instrumentation for neutron fluence rate (flux) measurements in power reactors (IEC 60568:2006)
- DIN EN ISO 10270:2020 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO/DIS 10270:2020); German and English version prEN ISO 10270:2020
Professional Standard - Nuclear Industry, reaction
- EJ/T 560-2002 Radiation surveillance of pressure vessels for Light-Water Cooled Reactors
- EJ/T 560-1991 Requirements for Irradiation Supervision of Reactor Pressure Vessel Materials
- 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 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 322-1994 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ 322-1988 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ/T 20032-2012 Design criteria for beryllium reflectors for space thermionic reactor nuclear power plants
- EJ/T 474-2000 Specification for reactor pressure vessel metal insulation for 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 606-1991 Ultrasonic In-Service Inspection of Reactor Pressure Vessel Welds in PWR Nuclear Power Plants
- EJ/T 478-1989 300,000-kilowatt pressurized water reactor nuclear power plant reactor pressure vessel top cover assembly
- EJ/T 712-2002 Installation requirements of reactor pressure vessel and its related equipment in PWR nuclear power plant
- EJ/T 1033-1996 Assessment criteria for preventing fast rupture of reactor pressure vessel of pressurized water reactor nuclear power plants
- EJ/T 918-1994 Guidelines for the formulation of pressure-temperature limit curves for reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ/T 20034-2012 Nuclear design criteria for space thermionic reactor 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 483-1989 Guidelines for Preparation of Technical Documentation for Reactor Pressure Vessels of 300MW Pressurized Water Reactor Nuclear Power Plant
- EJ/T 319-1992 Thermal-hydraulic Design Criteria for Pressurized Water Reactor Nuclear Power Plant
- EJ/T 20033-2012 Thermal Fluid Dynamics Design Criteria for Space Thermionic Reactor Nuclear Power Plant
- EJ 474-1989 300,000-kilowatt pressurized water reactor nuclear power plant Reactor Pressure Vessel Metal Foil Insulation Layer Technical Specifications
- EJ/T 20132-2016 Design criterion for thermionic fuel elements of space nuclear power system with thermionic reactor
- EJ/T 667-1992 Overpressure protection for low pressure systems connected to reactor coolant pressure boundaries
Professional Standard - Energy, reaction
- NB/T 20220-2013 Irradiation surveillance of reactor pressure vessels (RPVs) for light-water cooled reactors
- NB/T 20343-2015 Design and fabrication specification for the thermal insulation of reactor vessel and reactor coolant pipings and equipments of PWR nuclear power plants
- NB/T 20343-2021 Code for design and manufacture of reactor pressure vessel and reactor coolant system piping and equipment insulation layer in pressurized water reactor nuclear power plant
- NB/T 20154-2012 Guideline of ageing management for PWR reactor pressure vessels
- NB/T 20576-2019 Analysis of Neutron Flux Rate of Reactor Pressure Vessel in PWR Nuclear Power Plant
- NB/T 20032-2010 Evaluation rule of pressurized thermal shock for reactor pressure vessel of PWR NPP
- NB/T 20045-2011 Technical regulation for construction and acceptance of reactor vessel installation in PWR nuclear power plant
- NB/T 20392-2016 Technical regulation for construction and acceptance of reactor vessel installation in passive PWR nuclear power plant
- NB/T 20476.6-2019 Renewal of Operating License for Nuclear Power Plants Part 6: Time-limited Aging Analysis of Reactor Pressure Vessels
- NB/T 20006.36-2017 Alloy steel for pressurized water reactor nuclear power plants.Part 36: 19MnNiMo steel forgings for reactor vessel core region
- NB/T 20006.37-2017 Alloy steel for pressurized water reactor nuclear power plants.Part 37: 19MnNiMo steel forgings for reactor vessel non-core region
- NB/T 20006.5-2012 Alloy steel for pressurized water reactor nuclear power plants.Part 5:Mn-Ni-Mo alloy steel forgings for reactor pressure vessel heads
- NB/T 20006.5-2021 Alloy Steels for Pressurized Water Reactor Nuclear Power Plants Part 5: Manganese-Nickel-Molybdenum Steel Forgings for Reactor Pressure Vessel Heads
- NB/T 20006.4-2011 Alloy steel for pressurized water reactor nuclear power plants.Part 4:Mn-Ni-Mo steel forgings for reactor pressure vessels nozzles
- NB/T 20006.4-2021 Alloy Steels for Pressurized Water Reactor Nuclear Power Plants Part 4: Manganese-Nickel-Molybdenum Steel Forgings for Reactor Pressure Vessel Nozzles
- NB/T 20006.17-2021 Alloy Steels for Pressurized Water Reactor Nuclear Power Plants Part 17: Manganese-Nickel-Molybdenum Steel Forgings for Reactor Pressure Vessel Flanges and Connecting Sections
- NB/T 20006.3-2011 Alloy steel for pressurized water reactor nuclear power plants.Part 3:Mn-Ni-Mo steel forgings for transition rings and flanges of reactor pressure vessels
- NB/T 20006.18-2019 Alloy steel for pressurized water reactor nuclear power plants-Part 18: Mn-Ni-Mo alloy steel forgings for closure heads of reactor pressure vessel
- NB/T 20006.3-2021 Alloy Steels for Pressurized Water Reactor Nuclear Power Plants Part 3: Manganese-Nickel-Molybdenum Steel Forgings for Reactor Pressure Vessel Transitions and Flanges
- NB/T 20006.1-2011 Alloy steel for pressurized water reactor nuclear power plants.Part 1:Mn-Ni-Mo steel forgings for reactor pressure vessel shells in the beltline region
- NB/T 20006.1-2021 Alloy steels for pressurized water reactor nuclear power plants Part 1: Manganese-nickel-molybdenum steel forgings for reactor pressure vessel shells subjected to strong irradiation
- NB/T 20006.2-2011 Alloy steel for pressurized water reactor nuclear power plants.Part 2:Mn-Ni-Mo steel forgings for reactor pressure vessel shells outside the beltline region
- NB/T 20006.2-2021 Alloy Steels for Pressurized Water Reactor Nuclear Power Plants Part 2: Manganese-Nickel-Molybdenum Steel Forgings for Reactor Pressure Vessel Shells Not Subject to Strong Irradiation
- NB/T 20447-2017RK Overpressure protection for low pressure systems connected to reactor coolant pressure boundaries
Professional Standard - Chemical Industry, reaction
RU-GOST R, reaction
- GOST 29243-1991 Plastics. Unsaturated polyester resins. Determination of reactivity at 80 °C. (conventional method)
- GOST 29326-1992 Plastics. Phenolic resins. Determination of reactivity of resols under acid conditions
- GOST R 50088-1992 Water-moderated water-cooled power reactors. General requirements to performing of neutron physical calculations
- GOST 28506-1990 Fuel assemblies in nuclear power WWER reactors. Fuel failure detection methods
American Nuclear Society (ANS), reaction
- ANS 19.3-2011 Steady-state neutronics methods for power reactor analysis
- ANS 2.8-1992 Determining Design Basis Flooding at Power Reactor Sites
- ANS 19.11-1997 Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors
- ANS 57.10-1996 Design Criteria for Consolidation of LWR Spent Fuel
- ANS 19.4-1976 A guide for acquisition and documentation of reference power reactor physics measurements for nuclear analysis verification
- ANS 58.14-1993 Safety and Pressure Integrity Classification Criteria for Light Water Reactors
- ANS 58.14-2011 (R 2017) Safety and Pressure Integrity Classification Criteria for Light Water Reactors
British Standards Institution (BSI), reaction
- BS IEC 62117:2000 Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown
- BS ISO 11271:2002 Soil quality - Determination of redox potential - Field method
- BS ISO 23468:2021 Reactor technology. Power reactor analyses and measurements. Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
- BS ISO 11358-3:2013 Plastics. Thermogravimetry (TG) of polymers. Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- BS ISO 11358-3:2014 Plastics. Thermogravimetry (TG) of polymers. Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- BS ISO 11358-3:2021 Plastics. Thermogravimetry (TG) of polymers. Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- BS EN 50216-5:2002 Power transformer and reactor fittings - Liquid level, pressure and flow indicators, pressure relief devices and dehydrating breathers
- 20/30406599 DC BS ISO 11358-3. Plastics. Thermogravimetry (TG) of polymers. Part 3. Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- BS EN 50216-1:2002 Power transformers and reactor fittings - General
- BS ISO 10270:1996 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- BS 5552:1978 Code of practice for in-core instrumentation for neutron fluence rate (flux) measurements in power reactors
- BS EN ISO 10270:1996 Corrosion of metals and alloys. Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- BS EN ISO 10270:2008 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- BS EN 50216-10:2009 Power transformer and reactor
fittings —
Part 10: Oil-to-air heat exchangers
- BS EN 50216-7:2002 Power transformers and reactor fittings - Electric pumps for transformer oil
- BS IEC 60568:2006 Nuclear power plants - Instrumentation important to safety - In-core instrumentation for neutron fluence rate (flux) measurements in power reactors
- BS EN 60076-22-2:2019 Power transformer and reactor cooling equipment - Removable radiators
American Welding Society (AWS), reaction
- WRC 386:1993 International Views on Reactor Pressure Vessel Integrity
International Organization for Standardization (ISO), reaction
- ISO 10979:1994 Identification of fuel assemblies for nuclear power reactors
- ISO 23468:2021 Reactor technology - Power reactor analyses and measurements - Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
- ISO 18075:2018 Steady-state neutronics methods for power-reactor analysis
- ISO 11358-3:2013 Plastics.Thermogravimetry (TG) of polymers.Part 3: Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- ISO 1716:2010 Reaction to fire tests for products - Determination of the gross heat of combustion (calorific value)
- ISO 1716:2018 Reaction to fire tests for products - Determination of the gross heat of combustion (calorific value)
- ISO 11358-3:2021 Plastics - Thermogravimetry (TG) of polymers - Part 3: Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- ISO 10270:1995 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
Korean Agency for Technology and Standards (KATS), reaction
- KS A ISO 10979-2012(2022) Identification of fuel assemblies for nuclear power reactors
- KS M ISO 11358-3-2017(2022) Plastics - Thermogravimetry(TG) of polymers - Part3: Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- KS M ISO 11358-3:2017 Plastics - Thermogravimetry(TG) of polymers - Part3: Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- KS C IEC 60568-2009(2019) In-core instrumentation for neutron fluence rate(flux) measurements in power reactor
- KS D ISO 10270:2003 Corrosion of metals and alloys-Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- KS D ISO 10270:2016 Corrosion of metals and alloys－Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- KS C IEC 60568:2009 In-core instrumentation for neutron fluence rate(flux) measurements in power reactor
American National Standards Institute （ANSI), reaction
- ANSI/ANS 19.10-2009 Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals
- ANSI/ANS 19.3-2011 Steady-State Neutronics Methods for Power Reactor Analysis
- ANSI/ANS 58.14-2011 Safety and Pressure Integrity Classification Criteria for Light Water Reactors
- ANSI/ANS 19.11-1997 Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors
Group Standards of the People's Republic of China, reaction
- T/BSRS 086-2022 Application of temperature monitors for irradiation supervision of reactor pressure vessel
- T/CNS 53-2021 Determination of residual stress in J-groove weld mockup of RPV head penetration
- T/CNEA 104.1-2021 PWR pressure boundary components—Equipments design and fabrication— Part 1:Reactor pressure vessel
- T/CNS 39-2020 Design criteria for the reactor protection system of high temperature gas-cooled reactor nuclear power plant
- T/CNS 30-2020 Design criteria for the reactor coolant systems of high temperature gas cooled reactor nuclear power plant
YU-JUS, reaction
Military Standard of the People's Republic of China-Commission of Science,Technology and Industry for National Defence, reaction
- GJB 5405-2005 Glossary of term:space nuclear power system with thermionic reactor
- GJB 843.19A-2005 Safety code of design for submarine nuclear power plants part 19: Reactor thermal-hydraulic design criteria
ANS - American Nuclear Society, reaction
- 19.3-2005 Determination of Steady-State Neutron Reaction-Rate Distributions and Reactivity of Nuclear Power Reactors
- 2.8-1981 DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR SITES
- 2.8-1992 Determining Design Basis Flooding at Power Reactor Sites
- 56.10-1982 Subcompartment Pressure and Temperature Transient Analysis in Light Water Reactors
- 2.12-1978 GUIDELINES FOR COMBINING NATURAL AND EXTERNAL MAN-MADE HAZARDS AT POWER REACTOR SITES
- 19.4-2017 A Guide for Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification
- 19.4-1976 A guide for acquisition and documentation of reference power reactor physics measurements for nuclear analysis verification
- 58.14-1993 Safety and Pressure Integrity Classification Criteria for Light Water Reactors
- 58.14-2011 Safety and Pressure Integrity Classification Criteria for Light Water Reactors
- 56.4-1983 Pressure and Temperature Transient Analysis for Light Water Reactor Containments
- 56.3-1977 Overpressure Protection of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary
CZ-CSN, reaction
SE-SIS, reaction
- SIS SS-ISO 4037:1985 X and y reference radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of photon energy
- SIS SS IEC 568:1981 Nuclear instrumentation - In-core instrumentation for neutron fluence r?te (flux) measurements in power reactors
- SIS SS IEC 737:1984 Nuclear instrumentation — In-core temperature or primary envelope temperature measurements in nuclear power reactors — Characteristics and test methods
IT-UNI, reaction
- UNI 7459-1975 Nuclear power plants. Power reactors. Criteria for protection systems.
Military Standard of the People's Republic of China-General Armament Department, reaction
- GJB 843.2-1990 Design Safety Regulations for Submarine Nuclear Power Plants Reactor Pressure Vessel Design Criteria
- GJB 5165-2003 Specification for reactor coolant pumps for nuclear submarine power plants
- GJB 843.19-1994 Design Safety Regulations for Submarine Nuclear Power Plants Reactor Thermal Hydraulic Design Criteria
- GJB 2911-1997 Specifications for starting primary neutron sources in submarine nuclear power plant reactors
国家市场监督管理总局、中国国家标准化管理委员会, reaction
- GB/T 33047.3-2021 Plastics—Thermogravimetry (TG) of polymers—Part 3: Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- GB/T 38316-2019 Test method of explosive power for organic peroxides and self-reactive substances
WRC - Welding Research Council, reaction
- BULLETIN 386-1993 INTERNATIONAL VIEWS ON REACTOR PRESSURE VESSEL INTEGRITY (COMPANION BULLETIN TO #387)
- BULLETIN 87-1963 CRITICAL F ACTORS IN THE INTERPRETATION OF RADIATION EFFECTS ON THE MECHANICAL PROPERTIES OF STRUCTURAL METALS COMMERCIAL IMPLICATIONS OF RADIATION EFFECTS ON REACTOR PRESSURE VESSEL DESIGN@ FABRICATI
国家能源局, reaction
- NB/T 20440-2017 Assessment criteria for rapid fracture prevention of reactor pressure vessels in pressurized water reactor nuclear power plants
- NB/T 20439-2017 Guidelines for developing pressure-temperature limit curves for reactor pressure vessels in pressurized water reactor nuclear power plants
- NB/T 20478.1-2018 Technical specifications for sealing rings of reactor pressure vessels in pressurized water reactor nuclear power plants Part 1: O-rings
- NB/T 20478.2-2018 Technical specifications for sealing rings of reactor pressure vessels in pressurized water reactor nuclear power plants Part 2: Type C sealing rings
- NB/T 20006.41-2018 Alloy steels for pressurized water reactor nuclear power plants Part 41: Steel rods for reactor pressure vessel bolts, nuts and washers
- NB/T 20447-2017 Overpressure protection of low-pressure systems connected to the reactor coolant pressure boundary
KR-KS, reaction
- KS M ISO 11358-3-2017 Plastics - Thermogravimetry(TG) of polymers - Part3: Determination of the activation energy using the Ozawa-Friedman plot and analysis of the reaction kinetics
- KS D ISO 10270-2016 Corrosion of metals and alloys－Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
International Electrotechnical Commission (IEC), reaction
- IEC 60568:1977 Incore instrumentation for the measurement of fluence in power reactors
- IEC 60737:1982 In-core temperature or primary envelope temperature measurements in nuclear power reactors. Characteristics and test methods
未注明发布机构, reaction
- GJB 843.2A-2017 Safety regulations for the design of submarine nuclear power plants Part 2: Design requirements for reactor pressure vessels
- GJB 8790-2015 Specification for reactor coolant pumps for submarine nuclear power plants
- NB 20478.1-2018 Technical specifications for sealing rings of reactor pressure vessels in pressurized water reactor nuclear power plants Part 1: O-rings
- NB 20478.2-2018 Technical specifications for sealing rings of reactor pressure vessels in pressurized water reactor nuclear power plants Part 2: Type C sealing rings
- NB 20006.41-2018 Alloy steels for pressurized water reactor nuclear power plants Part 41: Steel rods for reactor pressure vessel bolts, nuts and washers
Association Francaise de Normalisation, reaction
- NF T57-402*NF EN ISO 14129:1998 Fibre-reinforced plastic composites. Determination of the in-plane shear stress/shear strain response, including the in-plane shear modulus and strength, by the plus over minus 45 degrees tension test method.
- NF P18-589:1992 Aggregates - Potential reactivity of alkali silica and alkali silicate type - Kinetic test - Chemical method
- NF P92-521:2013 Reaction to fire tests for products - Determination of the gross heat of combustion (calorific value)
- NF A05-401:2008 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors.
- NF A05-401*NF EN ISO 10270:2022 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
- NF C52-216-12*NF EN 50216-12:2011 Power transformer and reactor fittings - Part 12 : fans.
SAE - SAE International, reaction
Society of Automotive Engineers (SAE), reaction
- SAE J2979-2012 Test Method for Vulcanized Rubber and Thermoplastic Elastomer Determination of Compressive Stress Relaxation (CSR) Response
- SAE ARP739-2008 GAS POWER SERVOS AND REACTION CONTROL SYSTEMS
ISA - International Society of Automation, reaction
- ISA 67.03-1982 Light Water Reactor Coolant Pressure Boundary Leak Detection
American Gear Manufacturers Association, reaction
AGMA - American Gear Manufacturers Association, reaction
- 11FTM06-2011 Reversed Gear Tooth Bending Stress and Life Evaluation
Canadian Standards Association (CSA), reaction
- CSA N290.11-2013 Requirements for reactor heat removal capability during outage of nuclear power plants (First Edition)
- CSA N285.8-05 UPD 1-2007 Technical requirements for in-service evaluation of zirconium alloy pressure tubes in CANDU reactors
- CSA N285.8-05-2005 Technical requirements for in-service evaluation of zirconium alloy pressure tubes in CANDU reactors First Edition
The American Road & Transportation Builders Association, reaction
- AASHTO DIVISION I 3.29 Moments, Shears, and Reactions(Standard Specifications for Highway Bridges, Div. 1 - Design)
American Society of Mechanical Engineers (ASME), reaction
- ASME N-618-2001 Use of a Reactor Pressure Vessel as a Transportation Containment System Section XI, Division 1; (SUPP 10)
- ASME N-664-2001 Performance Demonstration Requirements for Examination of Unclad Reactor Pressure Vessel Welds, Excluding Flange Welds Section XI, Division 1; Supp 6
Canadian General Standards Board （CGSB), reaction
European Committee for Standardization (CEN), reaction
- EN ISO 10270:2022 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO 10270:2022)
- EN ISO 10270:2008 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO 10270:1995, including Cor 1:1997)
- FprEN ISO 10270:2021 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors (ISO/FDIS 10270:2021)
Danish Standards Foundation, reaction
- DS/EN ISO 10270:2009 Corrosion of metals and alloys - Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
Institute of Electrical and Electronics Engineers (IEEE), reaction
- IEEE Std C57.127-2018 IEEE Guide for the Detection, Location and Interpretation of Sources of Acoustic Emissions from Electrical Discharges in Power Transformers and Power Reactors
- IEEE PC57.127/D3, October 2017 IEEE Draft Guide for the Detection, Location and Interpretation of Sources of Acoustic Emissions from Electrical Discharges in Power Transformers and Power Reactors
- IEEE PC57.127/D4, July 2018 IEEE Approved Draft Guide for the Detection, Location and Interpretation of Sources of Acoustic Emissions from Electrical Discharges in Power Transformers and Power Reactors
GOSTR, reaction
- GOST R 50.05.12-2018 Conformity assessment system for the use of nuclear energy. Conformity assessment in the form of control. Control of reactor pressure vessels radiation embrittlement
- GOST R 59109-2020 Elements of reaction tube furnaces working under pressure. Specifications
IEEE - The Institute of Electrical and Electronics Engineers@ Inc., reaction
- IEEE PC57.127/D3-2017 Draft Guide for Detection@ Location and Interpretation of Sources of Acoustic Emissions from Electrical Discharges in Power Transformers and Power Reactors
- IEEE PC57.127/D4-2018 Draft Guide for Detection@ Location and Interpretation of Sources of Acoustic Emissions from Electrical Discharges in Power Transformers and Power Reactors