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Database: 365,228(8 Aug 2026)

reactor

reactor, Total:124 items.

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

The Chinese standard classification for "reactor" includes: Nuclear reactor and nuclear island equipment of nuclear power plant , Power reactor , Basic standards and general method , General nuclear instrument , Nuclear instrument for reactor , Medical nuclear instrument , Environmental radiation protection and nuclear medicine protection , Nuclear fuel element and its analytical test method , Nuclear island of nuclear power plant , Radiation protection and monitoring in general .


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

  • GB 12789.3-1992 Nuclear Reactor Instrumentation Guidelines Part III: High Temperature Gas Cooled Reactors
  • GB/T 41591-2022 Initial criticality tests for pressurized water reactor of nuclear power plants
  • GB/T 42144-2022 Calculation of doses to the public from discharge of effluents from reactor
  • GB/T 4960.2-1996 Glossary of terms:nuclear science and technology--Fission reactor
  • GB/T 12789.2-1991 Criteria for nuclear reactor instrumentation Part 2:pressurized water reactors
  • 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/T 5963-1995 Separation criteria for reactor protection system
  • GB/T 12789.4-1994 Criteria for nuclear reactor instrumentation-Part 4: Liguid-metal cooled fast reactors
  • GB/T 12789.1-1991 Criteria for nuclear reactor instrumentation--Part 1: General principes
  • GB/T 4083-2005 General safety principles of unclear reactor protection system
  • GB/T 14588-2009 Technical regulations for environmental management of reactor decommissioning
  • GB/T 12789.3-1992 Criteria for nuclear reactor reactor instrumentation Part three. High temperature gas-cooled reactor(HTGR)
  • GB 11850-1989 Regulation for radiation protection of reactor decommissioning
  • GB/T 13368-1992 Specifiation of nuclear fuel rods for miniature neutron source reactor
  • GB/T 5203-1985 Safety logic assemblies of nuclear reactor characteristics and test methods
  • GB/T 13628-1992 Nuclear reactor use of the protection system for non-safety purpose
  • GB/T 13368-2008 Specification for nuclear fuel rods of miniature neutron source reactor

Professional Standard - Nuclear Industry

  • EJ/T 20044-2014 Design criteria for sodium cooled fast breeder reactor.General design of reactor structure
  • EJ/T 560-2002 Radiation surveillance of pressure vessels for Light-Water Cooled Reactors
  • EJ/T 737-1992 General Principles of Reactor Noise Analysis
  • 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 503-1990 300MW Pressurized Water Reactor Nuclear Power Plant Reactor Internals Design and Manufacturing Specifications
  • EJ 322-1988 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
  • EJ/T 1137-2001 Design Specification for PWR control rod drive mechanism
  • EJ/T 732-1992 Evaluation criteria for pressurized thermal shock of reactor pressure vessels in pressurized water reactor nuclear power plants
  • EJ/T 712-2002 Installation requirements of reactor pressure vessel and its related equipment in PWR nuclear power plant
  • EJ/T 1113-2000 Initial critical test in PWR nuclear power plant
  • EJ/T 319-1992 Thermal-hydraulic Design Criteria for Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 1014-2005 Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors
  • EJ/T 560-1991 Requirements for Irradiation Supervision of Reactor Pressure Vessel Materials
  • EJ/T 445-1989 Reactor and Power Distribution Abnormal Analysis of 300MW PWR Nuclear Power Plant
  • EJ 622-1992 Reactor Fuel Element Terminology
  • EJ/T 763-1993 Light water test research reactor water quality technical conditions
  • EJ/T 959-1995 Data Processing Method for Thermal Neutron Flux Measurement in Nuclear Reactor
  • EJ/T 493-1989 300MW PWR Nuclear Power Plant Reactor Core Neutron Flux Measurement System Piping Design Regulations
  • EJ/T 322-1994 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
  • EJ/T 1238-2014 Physics and thermal design requirements for reactor fuel assembly irradiation test
  • EJ/T 474-2000 Specification for reactor pressure vessel metal insulation for pressurized water reactor nuclear power plants
  • EJ/T 20014-2012 Design Requirements for Irradiation Test Circuit of Water-cooled Reactor Fuel Assembly
  • EJ/T 733-1992 Method for Measurement of Uranium Contamination of PWR fuel rod surface
  • EJ/T 758-1993 Criteria for analysis of reactor bomb accidents in pressurized water nuclear power plants
  • EJ/T 478-1989 300,000-kilowatt pressurized water reactor nuclear power plant reactor pressure vessel top cover assembly
  • EJ/T 320-1998 General design criteria of reactor for pressurized water reactor nuclear power plants
  • EJ/T 446-1989 300MW PWR nuclear power plant reactor physical start-up test
  • EJ/T 20013-2012 Design requirements for irradiation testing device for water-cooled reactor fuel assemblies
  • 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 320-1988 General Design Guidelines for Reactor Structure of Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 318-1992 Reactor Design Criteria for Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 653-1998 Specification for fuel assembly of high flux engineering test reactor
  • EJ/T 1114-2000 Initial loading test for PWR nuclear power plant
  • EJ/T 675-1992 Fission ionization chamber for reactor
  • 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 444-1989 Regulations on Nuclear Design Contents of 300MW Pressurized Water Reactor Nuclear Power Plant
  • EJ/T 325-1988 Design criteria for reactor coolant system in pressurized water 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 836-1994 Pulse Reactor Commissioning Program
  • EJ 326-1988 Design criteria for reactor coolant auxiliary systems in pressurized water reactor nuclear power plants
  • EJ/T 1115-2000 Physics tests at low power for PWR nuclear power plant
  • EJ/T 853-1994 Design and application of microreactor beryllium reflector
  • EJ/T 567-1991 Nuclear Reactor Instrumentation Terminology
  • EJ/T 448-1989 Technical Specifications for Reactor Coolant Pumps of 300MW PWR Nuclear Power Plant

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

  • GJB 8790-2015 Specification for reactor coolant pumps for submarine nuclear power plants
  • GJB 820A-2018 Specification for coatings for submarine reactor compartments

Liaoning Provincial Standard of the People's Republic of China

国家能源局

  • NB/T 20435-2017 Physics tests for pressurized water reactor of nuclear power plants commissioning startup
  • NB/T 20434-2017 Initial loading test for pressurized water reactor of nuclear power plant

Professional Standard - Energy

  • NB/T 20304-2014 Technical guideline for installation of reactor protection system of pressured water reactor nuclear power plants
  • NB/T 20032-2010 Evaluation Rule of Pressurized Thermal Schock for Reactor Pressure Vessel of PWR NPP
  • NB/T 20057.3-2012 PWR Nuclear Power Plants Reactor System Design - Core - Part 3: Fuel Assembly
  • NB/T 20101-2012 Analysis Requirement for Rod Ejection Accidents of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20057.4-2012 PWR Nuclear Power Plants Reactor System Design - Core - Part 4: Core Components
  • NB/T 20064-2012 Installation and Test Requirement of In-core Instrumentation System in Pressured Water Reactor Nuclear Power Plant
  • NB/T 20187-2012 Design Criteria for Reactor Coolant System in Pressurized Water Reactor Nuclear Power Plants
  • 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 20173-2012 Technical Specification for Installation and Test of Ring Crane in Reactor Building of PWR Nuclear Power Plants
  • NB/T 20109-2012 Technical Specification of Neutron Flux Guide Tube Installation in Reactor Building for PWR Nuclear Power Plant
  • NB/T 20057.1-2012 Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 1: Nuclear Design
  • NB/T 20254-2013 Code for the Leakage Detection of Reactor Coolant System in Nuclear Power Plants
  • NB/T 20285-2014 General requirements of reactor system design for pressurized water reactor nuclear power plants
  • NB/T 20154-2012 Guideline of Ageing Management for PWR Reactor Pressure Vessels
  • NB/T 20102-2012 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
  • NB/T 20112-2012 Technical Regulation of the Cable Terminal Connection in the Reactor Building for PWR Nuclear Power Plant
  • NB/T 20107-2012 Technical Regulation for Construction of Reactor Coolant Pump Installation in PWR Nuclear Power Plant
  • NB/T 20269-2014 Design and fabrication specification for reactor coolant pump of pressurized water ractor nuclear power plant
  • NB/T 20220-2013 Radiation Surveillance of Pressure Vessels for Light-Water Cooled Reactors
  • NB/T 20099-2012 Analysis Demand for Loss-of-coolant Accident of Pressurized Water Reactor Nuclear Power Plants
  • NB/T 20045-2011 Technical Regulation for Construction and Acceptance of Reactor Vessel Installation in PWR Nuclear Power Plant
  • NB/T 20144-2012 Initial Criticality Tests for Pressurized Water Reactor of Nuclear Power Plants
  • NB/T 20334-2015 General requirements for noise analysis of reactor and primary loop in pressurized water reactor nuclear power plant

Professional Standard - Electricity

  • DL/T 1142-2009 Suftwarae test for reactur cuntrul systemof nuelear popear power plants

Inner Mongolia Provincial Standard of the People's Republic of China

  • DB15/T 714-2014 Straw Bioreactor Fermentation Facility Cultivation Technical Regulations
  • DB1504/T 1006-2018 Technical specification for solar greenhouse corn straw reactor
  • DB15/T 1381-2018 Technical specification for solar greenhouse built-in straw reactor

Ningxia Provincial Standard of the People's Republic of China

  • DB64/T 1779-2021 Technical regulations for facility fruit tree straw bioreactor

Heilongjiang Provincial Standard of the People's Republic of China

  • DB23/T 2619-2020 Technical Regulations for Cultivation of Strawberry with Built-in Straw Reactor in Greenhouse

Group Standards of the People's Republic of China

  • T/BSRS 086-2022 Application of temperature monitors for irradiation supervision of reactor pressure vessel
  • T/CNS 30-2020 Design criteria for the reactor coolant systems of high temperature gas cooled reactor nuclear power plant
  • T/CNS 39-2020 Design criteria for the reactor protection system of high temperature gas-cooled reactor nuclear power plant

国家市场监督管理总局、中国国家标准化管理委员会

  • GB/T 7164-2022 Characteristics and test methods of radiation detectors for nuclear reactors

Spanish Association for Standardization (UNE)

Korean Agency for Technology and Standards (KATS)

SCC

CENELEC - European Committee for Electrotechnical Standardization

British Standards Institution (BSI)

  • BS EN 60289:1994 Reactors
  • BS ISO 4233:2023 Reactor technology. Nuclear fusion reactors. Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors

HU-MSZT

  • MNOSZ 2960-1951 Technology Thermal Reactor Plan Thermal Reactor Equipment Logo

TR-TSE

International Electrotechnical Commission (IEC)

  • IEC 61505:1998 Nuclear reactor instrumentation - Boiling water reactors (BWR) - Stability monitoring
  • IEC 61343:1996 Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core
  • IEC 60231D:1975 General principles of nuclear reactor instrumentation

ES-AENOR

ISA - International Society of Automation

American Society of Mechanical Engineers (ASME)

SE-SIS

  • SIS SS IEC 639:1981 Nuclear instrumentation - Nuclear reactors - Use of the protection system for non-safety purposes

Defense Logistics Agency

GOSTR

IAEA - International Atomic Energy Agency