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Database: 365,228(8 Aug 2026)

deuterium-tritium reaction

deuterium-tritium reaction, Total:142 items.

The international standard classification for "deuterium-tritium reaction" includes: Reactor engineering , Nuclear energy engineering .

The Chinese standard classification for "deuterium-tritium reaction" includes: Nuclear instrument for reactor , Nuclear reactor and nuclear island equipment of nuclear power plant , Medical nuclear instrument , Basic standards and general method , Quantity and Unit , Animal quarantine, veterinary and epidemic prevention .


Group Standards of the People's Republic of China

  • T/CECPA 003-2021 Validation Method for Reactor Nuclear Design Software
  • T/BPCT 001-2024 Determination of the degree of deuteration in deuterated chloroform—Nuclear magnetic resonance spectroscopy
  • T/BSRS 029-2020 Technical specification for the analysis of tritium in liquid effluents for nuclear power plants
  • T/TAIA 003-2024 Chemical reagent—Determination of deuteration ratio of deuterated chloroform—1H NMR method

Professional Standard - Nuclear Industry

  • EJ/T 1014-2005 Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors
  • EJ/T 20029-2012 Nuclear Criticality Safety Nuclear Criticality Accident Emergency Preparedness and Response for Fissile Materials Outside the Reactor
  • EJ/T 318-1992 Reactor Design Criteria for Pressurized Water Reactor Nuclear Power Plants
  • EJ/T 567-1991 Nuclear Reactor Instrumentation Terminology
  • EJ/T 20034-2012 Nuclear design criteria for space thermionic reactor nuclear power plant

Professional Standard - Energy

  • NB/T 20102-2012 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors

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 3102.10-1993 Quantities and units of nuclear reactions and ionizing radiations
  • GB/T 4083-1983 General safety principles of nuclear reactor protection system
  • GB/T 4083-2005 General safety principles of unclear reactor protection system
  • GB/T 4960.2-1996 Glossary of terms:nuclear science and technology--Fission reactor
  • GB/T 12789.3-1992 Criteria for nuclear reactor reactor instrumentation Part three. High temperature gas-cooled reactor(HTGR)

未注明发布机构

  • DIN 25463-1 E:2012-12 Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors
  • DIN 25463-2 E:2012-12 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 25433 E:2015-12 Fuel assembly identification for nuclear power reactors

Taiwan Provincial Standard of the People's Republic of China

国家技术监督局

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

Professional Standard - Commodity Inspection

  • SN/T 1685-2005 Procedure of intradermal reaction test with old tuberculin for monkey tuberculosis
  • SN/T 1310-2003 Protocol of intradermal test for monkey tuberculosis

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

  • GJB 4256-2001 Safety requirements for external nuclear criticality of nuclear submarine reactor fuel elements

RO-ASRO

HU-MSZT

SE-SIS

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

ANS - American Nuclear Society

  • 19.3-1983 DETERMINATION OF NEUTRON REACTION RATE DISTRIBUTIONS AND REACTIVITY OF NUCLEAR REACTORS
  • 19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
  • 19.3-2005 Determination of Steady-State Neutron Reaction-Rate Distributions and Reactivity of Nuclear Power Reactors
  • 2.23-2002 Nuclear Plant Response to an Earthquake
  • 19.3.4-1976 Determination of Thermal Energy Deposition Rates in Nuclear Reactors
  • 19.3.4-2002 The Determination of Thermal Energy Deposition Rates in Nuclear Reactors

SCC

American Nuclear Society (ANS)

  • ANS 19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
  • ANS 2.23-2002 Nuclear Plant Response to an Earthquake
  • ANS 8.23-2007 Nuclear Criticality Accident Emergency Planning and Response
  • ANS 19.1-2002 nuclear data sets for reactor design calculations
  • 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)

American Society of Mechanical Engineers (ASME)

British Standards Institution (BSI)

  • 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 20041-1:2022 Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations - Sampling of tritium and carbon-14
  • BS 4877:2016 Nuclear reactor instrumentation and control. Code of practice
  • 21/30434328 DC BS EN 63374. Nuclear power plants. Instrumentation systems important to safety. Characteristic and test methods of nuclear reactor reactivity meter
  • BS ISO 10645:2022 Nuclear energy. Light water reactors. Decay heat power in non-recycled nuclear fuels

International Electrotechnical Commission (IEC)

  • IEC 61505:1998 Nuclear reactor instrumentation - Boiling water reactors (BWR) - Stability monitoring
  • IEC 60231:1967 General principles of nuclear reactor instrumentation
  • IEC 60557:1982 I E C terminology in the nuclear reactor field
  • IEC 61343:1996 Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core
  • IEC 60232:1966 General characteristics of nuclear reactor instrumentation
  • IEC 60231D:1975 General principles of nuclear reactor instrumentation
  • IEC 60231A:1969 General principles of nuclear reactor instrumentation

Korean Agency for Technology and Standards (KATS)

Association Francaise de Normalisation

  • NF M60-309:2001 Nuclear energy - Nuclear fuel technology-Waste - Tritium releasing assay in tritiated waste packages by ionization chamber
  • NF M60-321:2005 Nuclear energy - Nuclear fuel cycle technology - Waste - Non-intrusive, non-destructive determination of the tritium activity of a package containing tritiated waste by measurement of helium-3 leakage from the package

American National Standards Institute (ANSI)

US-FCR

Indonesia Standards

RU-GOST R

IAEA - International Atomic Energy Agency

  • 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

TR-TSE

  • TS 2596-1977 General Characteristics of Nuclear Reactor Instn?mentation
  • TS 1827-1975 QUANTITIES AND UNITS OF NUCLEAR REACTIONS AND IONIZING RADIATIONS

CZ-CSN

GSO

KR-KS

IT-UNI

  • UNI 7305-1974 Nuclear equipment: reactor. Radiated Steel Inspection
  • UNI 7555-1976 Nuclear equipment. Original circulation pump for water reactor

German Institute for Standardization

  • 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 25463-2:2014 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 25463-1:2014 Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors
  • DIN 25433:1988 Fuel assembly identification for nuclear power reactors
  • DIN 25411:1991 Nuclear reactors; graphical symbols and short forms
  • DIN 25433:2016 Fuel assembly identification for nuclear power reactors

International Organization for Standardization (ISO)

  • ISO 4233:2023 Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
  • ISO 12749-5:2018 Nuclear energy, nuclear technologies, and radiological protection - Vocabulary - Part 5: Nuclear reactors
  • ISO 10645:1992 Nuclear energy; light water reactors; calculation of the decay heat power in nuclear fuels
  • ISO 10979:1994 Identification of fuel assemblies for nuclear power reactors
  • ISO 20041-1:2022 Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 1: Sampling of tritium and carbon-14

U.S. Military Regulations and Norms