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neutron nucleus
neutron nucleus, Total:59 items.
In the international standard classification, neutron nucleus involves: Radiation protection, Radiation measurements, Nuclear energy engineering, Installations in buildings, Analytical chemistry.
American Nuclear Society (ANS), neutron nucleus
- ANS 8.24-2007 validation of neutron transport methods for nuclear criticality safety calculations
- ANS 8.21-1995 use of fixed neutron absorbers in nuclear facilities outside reactors
- ANS 6.1.2-1999 Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
- ANS 8.14-2004 use of soluble neutron absorbers in nuclear facilities outside reactors
- ANS 19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
National Metrological Verification Regulations of the People's Republic of China, neutron nucleus
- JJG(核工) 2-1991 Radionuclide Neutron Source Intensity Verification Regulations
Association Francaise de Normalisation, neutron nucleus
- NF M60-761-3:2008 Nuclear energy - Measurement of radioactivity in the environment - Water - Part 3 : radon 222 and its short-lived daughters in water : measurements by degassing.
- NF M60-516:1989 NEUTRON REFERENCE RADIATIONS FOR CALIBRATING NEUTRON-MEASURING DEVICES USED FOR RADIATION PROTECTION PURPOSES AND FOR DETERMINING THEIR RESPONSE AS A FUNCTION OF NEUTRON ENERGY.
Professional Standard - Nuclear Industry, neutron nucleus
- EJ/T 844-1994 Manganese Bath Method for Intensity Measurement of Radionuclide Neutron Sources
- EJ/T 915-2014 Medium efficiency air filters
- EJ 916-1994 Nuclear-grade medium-efficiency air particle filter
- EJ/T 20045-2014 Design criteria for sodium cooled fast breeder reactor.Nuclear design
- EJ/T 810-1994 One-time start-up of neutron source rods in pressurized water reactor nuclear power plants
- EJ/T 959-1995 Data Processing Method for Thermal Neutron Flux Measurement in Nuclear Reactor
- EJ/T 20100-2016 License examination for operators of sodium cooled fast breeder reactor
- EJ/T 20112-2016 Design criteria for sodium cooled fast breeder reactor.Nuclear power steam conversion system
- EJ/T 499-2004 Specification for design and manufacture of primary neutron source rod for pressurized water reactor nuclear power plant
- EJ/T 1014-2005 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, neutron nucleus
- 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/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
Japanese Industrial Standards Committee (JISC), neutron nucleus
- JIS Z 4416:2005 Solid state nuclear track dosemeter for personal neutron monitoring
American National Standards Institute (ANSI), neutron nucleus
- ANSI/ANS 8.21-1995 Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors
- ANSI/ANS 8.24-2017 Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations
- ANSI/ANS 8.24-2007 Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations
- ANSI/ANS 8.14-2004 Use of Soluble Neutron Absorbers in Nuclear Facilities Outside Reactors
European Committee for Electrotechnical Standardization(CENELEC), neutron nucleus
- HD 475 S1-1986 Dimensions of Planchets Used in Nuclear Electronic Instruments
American Society for Testing and Materials (ASTM), neutron nucleus
- ASTM E2059-15 Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM E205-96(2000) Standard Specification for Glass and Oxygen Combustion Flask
- ASTM E2059-20 Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM E205-96(2016) Standard Specification for Glass and Oxygen Combustion Flask
- ASTM E2059-06 Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM E2059-05 Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM D6031/D6031M-96(2010)e1 Standard Test Method for Logging In Situ Moisture Content and Density of Soil and Rock by the Nuclear Method in Horizontal, Slanted, and Vertical Access Tubes
- ASTM D7301-21 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
- ASTM C1493-19 Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System
- ASTM D6031-96(2004) Standard Test Method for Logging In Situ Moisture Content and Density of Soil and Rock by the Nuclear Method in Horizontal, Slanted, and Vertical Access Tubes
- ASTM D6031-96 Standard Test Method for Logging In Situ Moisture Content and Density of Soil and Rock by the Nuclear Method in Horizontal, Slanted, and Vertical Access Tubes
- ASTM D7301-11 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
- ASTM E2059-00a Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM E2059-06(2010) Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM E2059-15e1 Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry
- ASTM C1493-01 Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System
- ASTM C1493-09 Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System
HU-MSZT, neutron nucleus
Lithuanian Standards Office , neutron nucleus
- LST HD 475 S1-2002 Dimensions of planchets used in nuclear electronic instruments (IEC 60248:1984)
ANS - American Nuclear Society, neutron nucleus
- 19.3-1983 DETERMINATION OF NEUTRON REACTION RATE DISTRIBUTIONS AND REACTIVITY OF NUCLEAR REACTORS
- 8.24-2017 Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations
- 8.21-1995 use of fixed neutron absorbers in nuclear facilities outside reactors
- 19.3-1995 Determination of Steady State Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors
- 6.1.2-1999 Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
- 6.1.2-1989 Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
- 6.1.2-1983 NEUTRON AND GAMMA-RAY CROSS SECTIONS FOR NUCLEAR RADIATION PROTECTION CALCULATIONS FOR NUCLEAR POWER PLANTS
- 8.24-2007 validation of neutron transport methods for nuclear criticality safety calculations
国家能源局, neutron nucleus
- NB/T 20522-2018 Nuclear power plant core neutron flux measurement refers to casing eddy current testing
Professional Standard - Energy, neutron nucleus
- NB/T 20150-2012 Characteristics and test methods of self-powered neutron detectors for nuclear power plants
- NB/T 20102-2012 Determination of steady state neutron reaction rate distributions and reactivity of nuclear reactors
RU-GOST R, neutron nucleus
- GOST 26847-1986 Neutron sources radionuclide closed on the base of plutonium-238-beryllium. Main parameters, sizes and technical specifications