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
- 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
- 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
- STAS 12327-1985 WATER Gamma nuclides mixture analysis
- STAS 6729/2-1984 Nuclear energv NUCLEAR REACTOR TECHNOLOGY Glossary
- STAS 6729/1-1982 Nuclear energy PHYSICS OF NUCLEAR REACTORS Glosaary
HU-MSZT
- MSZ 14345/2-1976 Nuclear energy, nuclear reactor concept
- MSZ 24030/2-1980 Nuclear reactor equipment storage classification
- MSZ 24030/1-1979 Nuclear reactor equipment classification, packaging and transportation
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
- ANS 19.3-2005 Determination of Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
- ANS 19.3-1983 Determination of Steady-State Neutron Reaction-Rate Distributions and Reactivity of Nuclear Power Reactors
- BS IEC 61505:1998 Nuclear reactor instrumentation. Boiling water reactors (BWR). Stability monitoring
- ANS 2.23-2002(W2016) Nuclear Plant Response to an Earthquake
- ANS 2.23-2016(R2020) Nuclear Plant Response to an Earthquake
- AENOR UNE 73107:1996 Fire protection in Nuclear Power Plants with light water reactors.
- UNE 73107:1996 FIRE PROTECTION IN NPPS WITH LIGHT WATER REACTORS.
- CSA N290.4-11:2011 Requirements for reactor control systems of nuclear power plants
- ANS 19.3.4-2022 The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
- CSA N290.4-2011(R2016) Requirements for Reactor Control of Systems of Nuclear Power Plants
- ANS 19.3.4-2002(R2017) The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
- CAN3-N290.4-M82-1982(R2011) Requirements for the Reactor Regulating Systems of CANDU Nuclear Power Plants
- CAN/CSA N285.6 SERIES-1988(R2000) Material Standards for Reactor Components for CANDU Nuclear Power Plants
- BS ISO 31-10:1992 Quantities and units-Nuclear reactions and ionizing radiations
- ANS 19.3.4-1976(R1989) The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
- CAN/CSA-N285.6 Series-1988(R2000) Material Standards for Reactor Components for CANDU Nuclear Power Plants
- CSA N285.6 Serié-2005 CANDU Nuclear Power Plant Reactor Component Material Standards
- CAN3 N290.4-M82-1982(R2006) Requirements for the Reactor Regulating Systems of CANDU Nuclear Power Plants
- CSA N285.6 Series-2005 Material Standards For Reactor Components For CANDU Nuclear Power Plants
- DIN 25463-1 E:2012 Draft Document - Calculation of the decay power in nuclear fuels of light water reactors - Part 1: Uranium oxide nuclear fuel for pressurized water reactors
- BS 4975:1973 Specification for prestressed concrete pressure vessels for nuclear reactors
- ANS 52.1-1983(R1988) Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants
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)
- 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
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)
- KS C IEC 60231D:2012 Fourth supplement:Principles of instrumentation for pressurized water reactors
- KS C IEC 60231:2012 General principles of nuclear reactor instrumentation
- KS D 3748-2008(2018) Steel for steam evaporator of nuclear reactor
- KS C IEC 60557-2016 IEC terminology in the nuclear reactor field
- KS C IEC 60557:2004 IEC terminology in the nuclear reactor field
- 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 60231-2022 General principles of nuclear reactor instrumentation
- KS D 3748-2008 Steel for steam evaporator of nuclear reactor
- KS C IEC 60231-2012(2022) General principles of nuclear reactor instrumentation
- KS D 3748-2023 Steel for steam evaporator of nuclear reactor
- KS A ISO 10645-2006(2021) Nuclear energy-Light water reactors-Calculation of the decay heat power in nuclear fuels
- KS A ISO 10645:2006 Nuclear energy-Light water reactors-Calculation of the decay heat power in nuclear fuels
- 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 A ISO 10979-2022 Identification of fuel assemblies for nuclear power reactors
- KS A ISO 10979-2012(2022) Identification of fuel assemblies for nuclear power reactors
- KS C IEC 61224:2012 Nuclear reactors-Response time in resistance temperature detectors(RTD)-In situ measurements
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)
- ANSI/ANS 2.23-2016 Nuclear Power Plant Response to an Earthquake
- ANSI/ANS 2.23-2002 Nuclear Plant Response to an Earthquake
- ANSI/ANS 19.1-2002 Nuclear Data Sets for Reactor Design Calculations
- ANSI/ANS 19.3.4-2002 Determination of Thermal Energy Deposition Rates in Nuclear Reactors
US-FCR
- FCR DOE 5480.6-1986 SAFETY OF DEPARTMENT OF ENERGY-OWNED NUCLEAR REACTORS
- FCR DOE 5480.30-1993 NUCLEAR REACTOR SAFETY DESIGN CRITERIA
- FCR DOE-STD-101-92-1992 COMPILATION OF NUCLEAR SAFETY CRITERIA FOR POTENTIAL APPLICATION TO DOE NONREACTOR NUCLEAR FACILITIES
Indonesia Standards
- 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
- GOST 23082-1978 Nuclear reactors. Terms and definitions
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
- CSN IEC 231:1994 General principles of nuclear reactor instrumentation
GSO
- GSO IEC 60231:2015 General principles of nuclear reactor instrumentation
- GSO ISO 10979:2013 Identification of fuel assemblies for nuclear power reactors
- GSO ISO 10645:2013 Nuclear energy -- Light water reactors -- Calculation of the decay heat power in nuclear fuels
- BH GSO ISO 10979:2016 Identification of fuel assemblies for nuclear power reactors
KR-KS
- KS D 3748-2008(2023) Steel for steam evaporator of nuclear reactor
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
- ARMY MIL-DTL-3628/34 K VALID NOTICE 3-2013 Badge, Qualification, Nuclear Reactor Operators, Army
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