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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

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




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