Document Center List of Standards on Fissile Materials And Nuclear Fuel Technology Including Raw Materials Radioactive Wastes, See 13.030.30
ICS Code 27.120.30
Return to ICS Index.Up to Level 2:
The following documents are a part of this series:
ASTM:
- ASTM-C1001 - Standard Test Method for Radiochemical Determination of Plutonium in Soil by Alpha Spectroscopy
- ASTM-C1004 - Matrix for LWR Spent Fuel Receiving and Storage (Withdrawn 1999)
- ASTM-C1008 - Standard Specification for Sintered (Uranium-Plutonium) Dioxide
Pellets—Fast Reactor Fuel (Withdrawn 2014) - ASTM-C1010 - Standard Guide for Acceptance, Checkout, and Pre-Operational Testing of a Nuclear Fuels Reprocessing Facility (Withdrawn 2001)
- ASTM-C1011 - Standard Guide for Selection or Specification of Electrodeless Conductivity Instruments for the Nuclear Fuel Cycle
- ASTM-C1020 - Matrix for Light Water Reactor Fuel Reprocessing (Withdrawn 1999)
- ASTM-C1022 - Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate
- ASTM-C1030 - Standard Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry
- ASTM-C1031 - Standard Specification for Nuclear-Grade Aluminum Oxide Powder
- ASTM-C1052 - Standard Practice for Bulk Sampling of Liquid Uranium Hexafluoride
- ASTM-C1062 - Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities
- ASTM-C1065 - Standard Specification for Nuclear-Grade Zirconium Oxide Powder
- ASTM-C1066 - Standard Specification for Nuclear Grade Zirconium Oxide Pellets
- ASTM-C1075 - Standard Practices for Sampling Uranium-Ore Concentrate
- ASTM-C1076 - Standard Specification for Nuclear Grade Hafnium Oxide Pellets
- ASTM-C1098 - Standard Specification for Nuclear-Grade Hafnium Oxide Powder
- ASTM-C1108 - Standard Test Method for Plutonium by Controlled-Potential Coulometry
- ASTM-C1110 - Standard Practice for Sample Preparation for X-Ray Emission Spectrometric Analysis of Uranium in Ores Using the Glass Fusion or Pressed Powder Method (Withdrawn 2014)
- ASTM-C1128 - Standard Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials
- ASTM-C1156 - Standard Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials
- ASTM-C1165 - Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H
2 SO4 at a Platinum Working Electrode - ASTM-C1168 - Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis
- ASTM-C1187 - Standard Guide for Establishing Surveillance Test Program for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment
- ASTM-C1188 - Standard Guide for Establishing a Quality Assurance Program for Uranium Conversion Facilities (Withdrawn 2017)
- ASTM-C1204 - Standard Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration
- ASTM-C1205 - Standard Test Method for The Radiochemical Determination of Americium-241 in Soil by Alpha Spectrometry
- ASTM-C1206 - Standard Test Method for Plutonium by Iron (II)/Chromium (VI) Amperometric Titration (Withdrawn 2015)
- ASTM-C1217 - Standard Guide for Design of Equipment for Processing Nuclear and Radioactive Materials
- ASTM-C1220 - Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste
- ASTM-C1221 - Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry
- ASTM-C1233 - Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
- ASTM-C1235 - Standard Test Method for Plutonium by Titanium(III)/Cerium(IV) Titration (Withdrawn 2005)
- ASTM-C1254 - Standard Test Method for Determination of Uranium in Mineral Acids by X-Ray Fluorescence
- ASTM-C1255 - Standard Test Method for Analysis of Uranium and Thorium in Soils by Energy Dispersive X-Ray Fluorescence Spectroscopy
- ASTM-C1267 - Standard Test Method for Uranium by Iron (II) Reduction in Phosphoric Acid Followed by Chromium (VI) Titration in the Presence of Vanadium
- ASTM-C1268 - Standard Test Method for Quantitative Determination of 241Am in Plutonium by Gamma-Ray Spectrometry
- ASTM-C1284 - Standard Practice for Electrodeposition of the Actinides for Alpha Spectrometry
- ASTM-C1287 - Standard Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma Mass Spectrometry
- ASTM-C1295 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
- ASTM-C1296 - Standard Test Method for Determination of Sulfur in Uranium Oxides and Uranyl Nitrate Solutions by X-Ray Fluorescence (XRF) (Withdrawn 2007)
- ASTM-C1297 - Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle Materials
- ASTM-C1307 - Standard Test Method for Plutonium Assay by Plutonium (III) Diode Array Spectrophotometry
- ASTM-C1334 - Standard Specification for Uranium Oxides with a 235U Content of Less Than 5 % for Dissolution Prior to Conversion to Nuclear-Grade Uranium Dioxide
- ASTM-C1344 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single-Standard Gas Source Mass Spectrometer Method (Withdrawn 2020)
- ASTM-C1346 - Standard Practice for Dissolution of UF
6 from P-10 Tubes - ASTM-C1347 - Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis
- ASTM-C1348 - Standard Specification for Blended Uranium Oxides with 235U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide (Withdrawn 2013)
- ASTM-C1380 - Standard Test Method for Determination of Uranium Content and Isotopic Composition by Isotope Dilution Mass Spectrometry (Withdrawn 2018)
- ASTM-C1408 - Standard Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method
- ASTM-C1411 - Standard Practice for The Ion Exchange Separation of Uranium and Plutonium Prior to Isotopic Analysis
- ASTM-C1413 - Standard Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal Ionization Mass Spectrometry
- ASTM-C1428 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer Method
- ASTM-C1429 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Double-Standard Multi-Collector Gas Mass Spectrometer
- ASTM-C1430 - Standard Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration
- ASTM-C1431 - Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
- ASTM-C1432 - Standard Test Method for Determination of Impurities in Plutonium: Acid Dissolution, Ion Exchange Matrix Separation, and Inductively Coupled Plasma-Atomic Emission Spectroscopic (ICP/AES) Analysis
- ASTM-C1441 - Standard Test Method for the Analysis of Refrigerant 114, Plus Other Carbon-Containing and Fluorine-Containing Compounds in Uranium Hexafluoride via Fourier-Transform Infrared (FTIR) Spectroscopy (Withdrawn 2022)
- ASTM-C1453 - Standard Test Method for the Determination of Uranium by Ignition and the Oxygen to Uranium (O/U) Atomic Ratio of Nuclear Grade Uranium Dioxide Powders and Pellets
- ASTM-C1454 - Standard Guide for Pyrophoricity/Combustibility Testing in Support of Pyrophoricity Analyses of Metallic Uranium Spent Nuclear Fuel (Withdrawn 2016)
- ASTM-C1455 - Standard Test Method for Nondestructive Assay of Special Nuclear Material Holdup Using Gamma-Ray Spectroscopic Methods
- ASTM-C1456 - Standard Test Method for Determination of Uranium or Gadolinium (or both) in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray Fluorescence (XRF)
- ASTM-C1457 - Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction
- ASTM-C1458 - Standard Test Method for Nondestructive Assay of Plutonium, Tritium and 241Am by Calorimetric Assay
- ASTM-C1462 - Standard Specification for Uranium Metal Enriched to Less Than 20 % 235U
- ASTM-C1474 - Standard Test Method for Analysis of Isotopic Composition of Uranium in Nuclear-Grade Fuel Material by Quadrupole Inductively Coupled Plasma-Mass Spectrometry
- ASTM-C1476 - Standard Test Method for Analysis of Urine for Technetium-99 by Inductively Coupled Plasma-Mass Spectrometry (Withdrawn 2011)
- ASTM-C1477 - Standard Test Method for Isotopic Abundance Analysis of Uranium Hexafluoride and Uranyl Nitrate Solutions by Multi-Collector, Inductively Coupled Plasma-Mass Spectrometry
- ASTM-C1490 - Standard Guide for the Selection, Training and Qualification of Nondestructive Assay (NDA) Personnel
- ASTM-C1493 - 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-C1502 - Standard Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide
- ASTM-C1514 - Standard Test Method for Measurement of 235U Fraction Using Enrichment Meter Principle
- ASTM-C1517 - Standard Test Method for Determination of Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy
- ASTM-C1553 - Standard Guide for Drying of Spent Nuclear Fuel
- ASTM-C1554 - Standard Guide for Materials Handling Equipment for Hot Cells
- ASTM-C1625 - Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances by Thermal Ionization Mass Spectrometry
- ASTM-C1636 - Standard Guide for Determination of Uranium-232 in Uranium Hexafluoride
- ASTM-C1672 - Standard Test Method for Determination of the Uranium, Plutonium or Americium Isotopic Composition or Concentration by the Total Evaporation Method Using a Thermal Ionization Mass Spectrometer
- ASTM-C1682 - Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
- ASTM-C1689 - Standard Practice for Subsampling of Uranium Hexafluoride
- ASTM-C1703 - Standard Practice for Sampling of Gaseous Uranium Hexafluoride for Enrichment
- ASTM-C1718 - Standard Test Method for Nondestructive Assay of Radioactive Material by Tomographic Gamma Scanning
- ASTM-C1742 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Double Standard Single-Collector Gas Mass Spectrometer Method (Withdrawn 2023)
- ASTM-C1769 - Standard Practice for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup (Withdrawn 2023)
- ASTM-C1770 - Standard Test Method for Determination of Loose and Tapped Bulk Densities of Small Quantities of Plutonium Oxide
- ASTM-C1771 - Standard Test Method for Determination of Boron, Silicon, and Technetium in Hydrolyzed Uranium Hexafluoride by Inductively Coupled Plasma—Mass Spectrometer After Removal of Uranium by Solid Phase Extraction
- ASTM-C1807 - Standard Guide for Nondestructive Assay of Special Nuclear Material (SNM) Holdup Using Passive Neutron Measurement Methods
- ASTM-C1816 - Standard Practice for The Ion Exchange Separation of Small Volume Samples Containing Uranium, Americium, and Plutonium Prior to Isotopic Abundance and Content Analysis
- ASTM-C1817 - Standard Test Method for The Determination of the Oxygen to Metal (O/M) Ratio in Sintered Mixed Oxide ((U, Pu)O
2 ) Pellets by Gravimetry - ASTM-C1832 - Standard Test Method for Determination of Uranium Isotopic Composition by Modified Total Evaporation (MTE) Method Using Thermal Ionization Mass Spectrometer
- ASTM-C1838 - Standard Practice for Cleaning for 1S and 2S Bottles
- ASTM-C1842 - Standard Test Method for The Analysis of Boron and Silicon in Uranium Hexfluoride via Fourier-Transform Infrared (FTIR) Spectroscopy
- ASTM-C1843 - Standard Test Method for Determining Moisture Content in Uranium-Ore Concentrate
- ASTM-C1844 - Standard Test Method for Determination of Uranium in Urine by Inductively Coupled Plasma Mass Spectrometer Following Nitric Acid Dilution
- ASTM-C1845 - Standard Practice for The Separation of Lanthanide Elements from Uranium Matrices Using High Pressure Ion Chromatography (HPIC) for Isotopic Analyses by Inductively Coupled Plasma Mass Spectrometry (ICP-MS)
- ASTM-C1853 - Standard Test Method for The Determination of Carbon (Total) Content in Mixed Oxide ((U, Pu)O
2 ) Sintered Pellets by Direct Combustion-Infrared Detection Method - ASTM-C1854 - Standard Test Method for Determination of Hydrogen (total from all sources) in Mixed Oxide ((U, Pu)O
2 ) Sintered Pellets by the Inert Gas Fusion Technique Followed by Thermal Conductivity Measurement - ASTM-C1865 - Standard Test Method for The Determination of Carbon and Sulfur Content in Plutonium Oxide Powder by the Direct Combustion-Infrared Spectrophotometer
- ASTM-C1868 - Standard Practice for Ceramographic Preparation of UO
2 and Mixed Oxide (U,Pu)O2 Pellets for Microstructural Analysis - ASTM-C1871 - Standard Test Method for Determination of Uranium Isotopic Composition by the Double Spike Method Using a Thermal Ionization Mass Spectrometer
- ASTM-C696 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets
- ASTM-C697 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets
- ASTM-C698 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O
2 ) - ASTM-C699 - Method for Chemical, Mass Spectrometric, and Spectrochemical Analysis of, and Physical Tests on Beryllium Oxide Powder (Withdrawn 1992)
- ASTM-C708 - Standard Specification for Nuclear-Grade Beryllium Oxide Powder (Withdrawn 2024)
- ASTM-C750 - Standard Specification for Nuclear-Grade Boron Carbide Powder
- ASTM-C751 - Standard Specification for Nuclear-Grade Boron Carbide Pellets
- ASTM-C753 - Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM-C757 - Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
- ASTM-C758 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium Metal
- ASTM-C759 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium Nitrate Solutions
- ASTM-C761 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride
- ASTM-C776 - Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
- ASTM-C784 - Standard Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets
- ASTM-C785 - Standard Specification for Nuclear-Grade Aluminum Oxide Pellets
- ASTM-C787 - Standard Specification for Uranium Hexafluoride for Enrichment
- ASTM-C788 - Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
- ASTM-C791 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Boron Carbide
- ASTM-C799 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
- ASTM-C809 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum
Oxide-Boron Carbide Composite Pellets - ASTM-C833 - Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
- ASTM-C853 - Test Method for Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste (Withdrawn 1992)
- ASTM-C859 - Standard Terminology Relating to Nuclear Materials
- ASTM-C888 - Standard Specification for Nuclear-Grade Gadolinium Oxide (Gd
2 O3 ) Powder - ASTM-C889 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd
2 O3 ) Powder - ASTM-C922 - Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
- ASTM-C934 - Guide for Design and Quality Assurance Practices for Nuclear Fuel Rods (Withdrawn 1995)
- ASTM-C967 - Standard Specification for Uranium Ore Concentrate
- ASTM-C968 - Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets
- ASTM-C970 - Standard Practice for Sampling Special Nuclear Materials in Multi-Container Lots (Withdrawn 2012)
- ASTM-C982 - Standard Guide for Selecting Components for Energy-Dispersive X-Ray Fluorescence (XRF) Systems (Withdrawn 2008)
- ASTM-C994 - Method for Ceramographic Preparation of PUO -UO Mixed Oxide Fuel Pellets and Uranium Pellets (Withdrawn 1991)
- ASTM-C996 - Standard Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U
- ASTM-C997 - Test Methods for Chemical and Instrumental Analysis of Nuclear-Grade Sodium and Cover Gas (Withdrawn 1999)
- ASTM-D5411 - Standard Practice for Calculation of Average Energy Per Disintegration (
E – - ASTM-D7219 - Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
- ASTM-E2089 - Standard Practices for Ground Laboratory Atomic Oxygen Interaction Evaluation of Materials for Space Applications
- ASTM-E217 - Test Method for Uranium by Controlled-Potential Coulometry (Withdrawn 1992)
- ASTM-E219 - Test Method for Atom Percent Fission in Uranium Fuel (Radiochemical Method) (Withdrawn 2001)
- ASTM-E261 - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
- ASTM-E262 - Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques
- ASTM-E263 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
- ASTM-E264 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
- ASTM-E265 - Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
- ASTM-E266 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
- ASTM-E267 - Standard Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances (Withdrawn 2006)
- ASTM-E318 - Test Method for Uranium in Aqueous Solutions by Colorimetry (Withdrawn 1996)
- ASTM-E321 - Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)
- ASTM-E385 - Standard Test Method for Oxygen Content Using a 14-MeV Neutron Activation and Direct-Counting Technique
- ASTM-E402 - Standard Test Method for Spectrographic Analysis of Uranium Oxide (U3O8)by Gallium Oxide-Carrier Technique (Withdrawn 2007)
- ASTM-E453 - Standard Practice for Examination of Fuel Element Cladding Including the Determination of the Mechanical Properties
- ASTM-E481 - Standard Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver
- ASTM-E496 - Standard Test Method for Measuring Neutron Fluence and Average Energy from 3H(d,n) 4He Neutron Generators by Radioactivation Techniques
- ASTM-E523 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
- ASTM-E526 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium
- ASTM-E669 - Master Matrix for Nuclear Fuel Cycle Standards (Withdrawn 2000)
- ASTM-E692 - Standard Test Method for Determining the Content of Cesium-137 in Irradiated Nuclear Fuels by High-Resolution Gamma-Ray Spectral Analysis (Withdrawn 2013)
- ASTM-E704 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
- ASTM-E705 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
- ASTM-E763 - Practice for Calculation of Absorbed Dose From Neutron Irradiation by Application of Threshold-Foil Measurement Data (Withdrawn 1997)
- ASTM-E846 - Matrix for Light-Water Reactor Spent Fuel Transportation (Withdrawn 1989)
- ASTM-E901 - Classification System for Uranium Resources (Withdrawn 2001)
BSI:
- BS-3598 - Fissile materials. Criticality safety in handling and processing. Recommendations
- BS-5288 - Specification. Sealed radioactive sources
- BS-EN-ISO-10276 - Nuclear energy. Fuel technology. Trunnion systems for packages used to transport radioactive material
- BS-EN-ISO-12183 - Nuclear fuel technology. Controlled-potential coulometric measurement of plutonium
- BS-EN-ISO-12183-TC - Tracked Changes. Nuclear fuel technology. Controlled-potential coulometric measurement of plutonium
- BS-EN-ISO-12799 - Nuclear energy. Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets. Inert gas extraction and conductivity detection method
- BS-EN-ISO-12800 - Nuclear fuel technology. Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method
- BS-EN-ISO-12807 - Safe transport of radioactive materials. Leakage testing on packages
- BS-EN-ISO-15366-1 - Nuclear fuel technology. Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography
- BS-EN-ISO-15366-2 - Nuclear fuel technology. Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography. Samples containing plutonium and uranium in the nanogram range and below
- BS-EN-ISO-15646 - Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets
- BS-EN-ISO-16424 - Nuclear energy. Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements
- BS-EN-ISO-16793 - Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
- BS-EN-ISO-18256-1 - Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials
- BS-EN-ISO-18256-2 - Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials
- BS-EN-ISO-18557 - Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
- BS-EN-ISO-19017 - Guidance for gamma spectrometry measurement of radioactive waste
- BS-EN-ISO-21483 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
- BS-EN-ISO-21484 - Nuclear Energy. Fuel technology. Determination of the O/M ratio in MOX pellets by the gravimetric method
- BS-EN-ISO-22765 - Nuclear fuel technology. Sintered (U,Pu)O2 pellets. Guidance for ceramographic preparation for microstructure examination
- BS-EN-ISO-8299 - Nuclear fuel technology. Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry
- BS-EN-ISO-9161 - Uranium dioxide powder. Determination of apparent density and tap density
- BS-EN-ISO-9463 - Nuclear energy. Nuclear fuel technology. Determination of plutonium in nitric acid solutions by spectrophotometry
- BS-ISO-10276 - Nuclear energy. Fuel technology. Trunnion systems for packages used to transport radioactive material
- BS-ISO-11320 - Nuclear criticality safety. Emergency preparedness and response
- BS-ISO-12183 - Nuclear fuel technology. Controlled-potential coulometric assay of plutonium
- BS-ISO-12799 - Nuclear energy. Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets. Inert gas extraction and conductivity detection method
- BS-ISO-12800 - Nuclear fuel technology. Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method
- BS-ISO-12807 - Safe transport of radioactive materials. Leakage testing on packages
- BS-ISO-13463 - Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel. Guidelines to help in the definition of a product specification
- BS-ISO-13465 - Nuclear energy. Nuclear fuel technology. Determination of neptunium in nitric acid solutions by spectrophotometry
- BS-ISO-15646 - Re-sintering test for UO$d2, (U,Gd)O$d2 and (U,Pu)O$d2 pellets
- BS-ISO-15651 - Nuclear energy. Determination of total hydrogen content in PuO$d2 and UO$d2 powders and UO$d2, (U,Gd)O$d2 and (U,Pu)O$d2 sintered pellets. Inert gas extraction and conductivity detection method
- BS-ISO-16424 - Nuclear energy. Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd$d2O$d3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements
- BS-ISO-16793 - Nuclear fuel technology. Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
- BS-ISO-16795 - Nuclear energy. Determination of Gd2O3 content in pellets containing uranium oxide by X-ray fluorescence spectrometry
- BS-ISO-16966 - Nuclear energy. Nuclear fuel technology. Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
- BS-ISO-1709 - Nuclear energy. Fissile materials. Principles of criticality safety in storing, handling and processing
- BS-ISO-18256-1 - Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials
- BS-ISO-18256-2 - Nuclear fuel technology. Dissolution of plutonium dioxide-containing materials
- BS-ISO-18315 - Nuclear energy. Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis
- BS-ISO-18557 - Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
- BS-ISO-19017 - Guidance for gamma spectrometry measurement of radioactive waste
- BS-ISO-21238 - Nuclear energy. Nuclear fuel technology. Scaling factor method to determine the radioactivity of low and intermediate-level radioactive waste packages generated at nuclear power plants
- BS-ISO-21391 - Nuclear criticality safety. Geometrical dimensions for subcriticality control. Equipment and layout
- BS-ISO-21483 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
- BS-ISO-21484 - Nuclear Energy. Fuel technology. Determination of the O/M ratio in MOX pellets by the gravimetric method
- BS-ISO-22765 - Nuclear fuel technology. Sintered (U,Pu)O2 pellets. Guidance for ceramographic preparation for microstructure examination
- BS-ISO-22875 - Nuclear energy. Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets
- BS-ISO-22946 - Nuclear criticality safety. Solid waste excluding irradiated and non-irradiated nuclear fuel
- BS-ISO-24459 - Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry
- BS-ISO-27467 - Nuclear criticality safety. Analysis of a postulated criticality accident
- BS-ISO-6863 - Nuclear fuel technology. Preparation of spikes for isotope dilution mass spectrometry (IDMS)
- BS-ISO-7195 - Nuclear energy. Packagings for the transport of uranium hexafluoride (UF6)
- BS-ISO-8299 - Nuclear fuel technology. Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry
- BS-ISO-8425 - Nuclear fuel technology. Determination of plutonium in pure plutonium nitrate solutions. Gravimetric method
- BS-ISO-9005 - Nuclear energy. Uranium dioxide powder and sintered pellets. Determination of oxygen/uranium atomic ratio by the amperometric method
- BS-ISO-9161 - Uranium dioxide powder. Determination of apparent density and tap density
- BS-ISO-9463 - Nuclear energy. Nuclear fuel technology. Determination of plutonium in nitric acid solutions by spectrophotometry
ISO:
- ISO-10276 - Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material
- ISO-10980 - Validation of the strength of reference solutions used for measuring concentrations
- ISO-10981 - Nuclear fuel technology - Determination of uranium in reprocessing-plant dissolver solution - Liquid chromatography method
- ISO-11311 - Nuclear criticality safety - Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors
- ISO-11311-AM1 - - Amendment 1: Nuclear criticality safety - Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors - Amendment 1: Corrections and clarifications
- ISO-11320 - Nuclear criticality safety - Emergency preparedness and response
- ISO-11482 - Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant
- ISO-11483 - Nuclear fuel technology - Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry
- ISO-12183 - Nuclear fuel technology - Controlled-potential coulometric measurement of plutonium
- ISO-12184 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O2
- ISO-12795 - Nuclear fuel technology - Uranium dioxide powder and pellets - Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction
- ISO-12799 - Nuclear energy - Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method
- ISO-12800 - Nuclear fuel technology - Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method
- ISO-12803 - Representative sampling of plutonium nitrate solutions for determination of plutonium concentration
- ISO-12807 - Safe transport of radioactive materials - Leakage testing on packages
- ISO-13463 - Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel -- Guidelines to help in the definition of a product specification
- ISO-13464 - Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants -- Combined method using K-absorption edge and X-ray fluorescence spectrometry
- ISO-13465 - Nuclear energy - Nuclear fuel technology - Determination of neptunium in nitric acid solutions by spectrophotometry
- ISO-15366 - Nuclear energy -- Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and dilution analysis by solvent chromatography
- ISO-15366-1 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range
- ISO-15366-2 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 2: Samples containing plutonium and uranium in the nanogram range and below
- ISO-15646 - Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets
- ISO-15647 - Nuclear energy - Isotopic analysis of uranium hexafluoride - Double-standard gas-source mass spectrometric method
- ISO-15651 - Nuclear energy - Determination of total hydrogen content in PuO2 and UO2 powders and UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method
- ISO-16424 - Nuclear energy - Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements
- ISO-16793 - Nuclear fuel technology - Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
- ISO-16794 - Nuclear energy - Determination of carbon compounds and fluorides in uranium hexafluoride infrared spectrometry
- ISO-16795 - Nuclear energy - Determination of Gd2O3 content in pellets containing uranium oxide by X-ray fluorescence spectrometry
- ISO-16796 - Nuclear energy - Determination of Gd2O3 content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES)
- ISO-16966 - Nuclear energy - Nuclear fuel technology - Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
- ISO-1709 - Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing
- ISO-1709-AM1 - - Amendment 1: Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing - Amendment 1: Methods of control and safety equipment
- ISO-18213-1 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 1: Procedural overview
- ISO-18213-2 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 2: Data standardization for tank calibration
- ISO-18213-3 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 3: Statistical methods
- ISO-18213-4 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 4: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, slow bubbling rate
- ISO-18213-5 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 5: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, fast bubbling rate
- ISO-18213-6 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 6: Accurate in-tank determination of liquid density in accountancy tanks equipped with dip tubes
- ISO-18256-1 - Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 1: Dissolution of plutonium dioxide powders
- ISO-18256-2 - Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 2: Dissolution of MOX pellets and powders
- ISO-18315 - Nuclear energy - Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis
- ISO-18557 - Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
- ISO-19017 - Guidance for gamma spectrometry measurement of radioactive waste
- ISO-21238 - Nuclear energy - Nuclear fuel technology - Scaling factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants
- ISO-21391 - Nuclear criticality safety - Geometrical dimensions for subcriticality control - Equipment and layout
- ISO-21483 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
- ISO-21484 - Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method
- ISO-21847-1 - Nuclear fuel technology - Alpha spectrometry - Part 1: Determination of neptunium in uranium and its compounds
- ISO-21847-2 - Nuclear fuel technology - Alpha spectrometry - Part 2: Determination of plutonium in uranium and its compounds
- ISO-21847-3 - Nuclear fuel technology - Alpha spectrometry - Part 3: Determination of uranium 232 in uranium and its compounds
- ISO-22765 - Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination
- ISO-22875 - Nuclear energy - Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets
- ISO-22946 - Nuclear criticality safety - Solid waste excluding irradiated and non-irradiated nuclear fuel
- ISO-24459 - Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry
- ISO-26062 - Nuclear technology - Nuclear fuels - Procedures for the measurement of elemental impurities in uranium- and plutonium-based materials by inductively coupled plasma mass spectrometry
- ISO-27467 - Nuclear criticality safety - Analysis of a postulated criticality accident
- ISO-27468 - Nuclear criticality safety - Evaluation of systems containing PWR UOX fuels - Bounding burnup credit approach
- ISO-6863 - Nuclear fuel technology - Preparation of spikes for isotope dilution mass spectrometry (IDMS)
- ISO-7097-1 - Nuclear fuel technology - Determination of uranium in solutions, uranium hexafluoride and solids - Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
- ISO-7097-2 - Nuclear fuel technology - Determination of uranium in solutions, uranium hexafluoride and solids - Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method
- ISO-7195 - Nuclear energy - Packagings for the transport of uranium hexafluoride (UF6)
- ISO-7476 - Nuclear fuel technology - Determination of uranium in uranyl nitrate solutions of nuclear grade quality - Gravimetric method
- ISO-8298 - Nuclear fuel technology - Determination of milligram amounts of plutonium in nitric acid solutions - Potentiometric titration with potassium dichromate after oxidation by Ce(IV) and reduction by Fe(II)
- ISO-8299 - Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry
- ISO-8300 - Nuclear fuel technology - Determination of plutonium content in plutonium dioxide of nuclear grade quality - Gravimetric method
- ISO-8425 - Nuclear fuel technology - Determination of plutonium in pure plutonium nitrate solutions - Gravimetric method
- ISO-9005 - Nuclear energy - Uranium dioxide powder and sintered pellets - Determination of oxygen/uranium atomic ratio by the amperometric method
- ISO-9006 - Uranium metal and uranium dioxide powder and pellets -- Determination of nitrogen content -- Method using ammonia-sensing electrode
- ISO-9161 - Uranium dioxide powder - Determination of apparent density and tap density
- ISO-9278 - Nuclear energy - Uranium dioxide pellets - Determination of density and volume fraction of open and closed porosity
- ISO-9279 - Uranium dioxide pellets -- Determination of density and total porosity -- Mercury displacement method
- ISO-9463 - Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry
- ISO-9889 - Determination of carbon content in uranium dioxide powder and sintered pellets -- Resistance furnace combustion -- Titrimetric/coulometric/infrared absorbtion method
- ISO-9891 - Determination of carbon content in uranium dioxide powder and sintered pellets -- High-frequency induction furnace combustion -- Titrimetric/coulometric/infrared absorption methods
- ISO-9892 - Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions -- Determination of fluorine content -- Fluoride ion selective electrode method
- ISO-9894 - Subsampling of uranium hexafluoride in the liquid phase
Other SDOs:
- AISC-C708 CD - Specification for Nuclear-Grade Beryllium Oxide Powder
- EN-ISO-12183 - Nuclear fuel technology - Controlled-potential coulometric assay of plutonium (ISO 12183:2016)
- EN-ISO-12799 - Nuclear energy - Determination of nitrogen content in UO<(Index)2>-, (U,Gd)O<(Index)2>- and (U,Pu)O<(Index)2> sintered pellets - Inert gas extraction and conductivity detection method (ISO 12799:2015)
- EN-ISO-12800 - Nuclear fuel technology - Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method (ISO 12800:2017)
- EN-ISO-15366-1 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range
- EN-ISO-15366-2 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 2: Samples containing plutonium and uranium in the nanogram range and below
- EN-ISO-15646 - Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets
- EN-ISO-15651 - Nuclear energy - Determination of total hydrogen content in PuO2 and UO2 powders and UO2, (U, Gd)O2 and (U, Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 15651:2015)
- EN-ISO-16424 - Nuclear energy - Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements
- EN-ISO-19017 - Guidance for gamma spectrometry measurement of radioactive waste
- EN-ISO-21483 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
- EN-ISO-21484 - Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method (ISO 21484:2017)
- EN-ISO-22765 - Nuclear fuel technology - Sintered (U,Pu)O<(Index)2> pellets - Guidance for ceramographic preparation for microstructure examination (ISO 22765:2016)
- JIS-Z-4820 - Test method for leakage of glove boxes
- SS-EN-10003-2 - Metallic materials - Brinell hardness test - Part2: Verification of Brinell hardness testing machines
- SS-EN-10003-3 - Metallic materials - Hardness testing - Calibration of standardised blocks to be used for Brinell hardness testing machines
- SS-EN-ISO-10276 - Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material (ISO 10276:2019)
- SS-EN-ISO-12183 - Nuclear fuel technology - Controlled-potential coulometric assay of plutonium (ISO 12183:2016)
- SS-EN-ISO-12799 - Nuclear energy - Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 12799:2015)
- SS-EN-ISO-12800 - Nuclear fuel technology - Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method (ISO 12800:2017)
- SS-EN-ISO-15366-1 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range (ISO 15366-1:2014)
- SS-EN-ISO-15366-2 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 2: Samples containing plutonium and uranium in the nanogram range and below (ISO 15366-2:2014)
- SS-EN-ISO-15646 - Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets (ISO 15646:2014)
- SS-EN-ISO-15651 - Nuclear energy - Determination of total hydrogen content in PuO2 and UO2 powders and UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 15651:2015)
- SS-EN-ISO-16424 - Nuclear energy - Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements (ISO 16424:2012)
- SS-EN-ISO-16796 - Nuclear energy - Determination of Gd2O3 content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES) (ISO 16796:2022)
- SS-EN-ISO-18526-2 - Eye and face protection - Test methods - Part 2 : Physical optical properties (ISO 18526-2:2020)
- SS-EN-ISO-18557 - Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes (ISO 18557:2017)
- SS-EN-ISO-19017 - Guidance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015)
- SS-EN-ISO-21483 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2 (ISO 21483:2013)
- SS-EN-ISO-21484 - Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method (ISO 21484:2017)
- SS-EN-ISO-22765 - Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination (ISO 22765:2016)
- SS-EN-ISO-24459 - Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry (ISO 24459:2021)
- SS-ISO-10276 - Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material (ISO 10276:2019, IDT)
- SS-ISO-10645 - Nuclear energy - Light water reactors - Calculation of the decay heat power in nuclear fuels
- SS-ISO-10980 - Validation of the strength of reference solutions used for measuring concentrations (ISO 10980:1995, IDT)
- SS-ISO-10981 - Nuclear fuel technology - Determination of uranium in reprocessing-plant dissolver solution - Liquid chromatography method (ISO 10981:2004, IDT)
- SS-ISO-11311 - Nuclear criticality safety - Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors (ISO 11311:2011, IDT)
- SS-ISO-11311-AM1 - Nuclear criticality safety - Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors - Amendment 1: Corrections and clarifications (ISO 11311:2011/Amd 1:2022, IDT)
- SS-ISO-11320 - Nuclear criticality safety - Emergency preparedness and response (ISO 11320:2011, IDT)
- SS-ISO-11482 - Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant (ISO 11482:1993, IDT)
- SS-ISO-11483 - Nuclear fuel technology - Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry (ISO 11483:2005, IDT)
- SS-ISO-12183 - Nuclear fuel technology - Controlled-potential coulometric assay of plutonium (ISO 12183:2016, IDT)
- SS-ISO-12184 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O2 (ISO 12184:1994, IDT)
- SS-ISO-12795 - Nuclear fuel technology - Uranium dioxide powder and pellets - Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction (ISO 12795:2004, IDT)
- SS-ISO-12799 - Nuclear energy - Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 12799:2015, IDT)
- SS-ISO-12800 - Nuclear fuel technology - Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method (ISO 12800:2017, IDT)
- SS-ISO-12803 - Representative sampling of plutonium nitrate solutions for determination of plutonium concentration (ISO 12803:1997, IDT)
- SS-ISO-12807 - Safe transport of radioactive materials - Leakage testing on packages (ISO 12807:2018, IDT)
- SS-ISO-13463 - Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel - Guidelines to help in the definition of a product specification (ISO 13463:1999, IDT)
- SS-ISO-13464 - Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants - Combined method using K-absorption edge and X-ray fluorescence spectrometry (ISO 13464:1998, IDT)
- SS-ISO-13465 - Nuclear Energy - Nuclear Fuel Technology - Determination of neptunium in nitric acid solutions by spectrophotometry (ISO 13465:2009, IDT)
- SS-ISO-15366 - Nuclear energy - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography
- SS-ISO-15366-1 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range (ISO 15366-1:2014, IDT)
- SS-ISO-15366-2 - Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 2: Samples containing plutonium and uranium in the nanogram range and below (ISO 15366-2:2014, IDT)
- SS-ISO-15646 - Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets (ISO 15646:2014, IDT)
- SS-ISO-15647 - Nuclear energy - Isotopic analysis of uranium hexafluoride - Double-standard gas-source mass spectrometric method (ISO 15647:2004, IDT)
- SS-ISO-15651 - Nuclear energy - Determination of total hydrogen content in PuO2 and UO2 powders and UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 15651:2015, IDT)
- SS-ISO-16424 - Nuclear energy - Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements (ISO 16424:2012, IDT)
- SS-ISO-16793 - Nuclear fuel technology - Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018, IDT)
- SS-ISO-16794 - Nuclear energy - Determination of carbon compounds and fluorides in uranium hexafluoride by infrared spectrometry (ISO 16794:2003, IDT)
- SS-ISO-16795 - Nuclear energy - Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry (ISO 16795:2004, IDT)
- SS-ISO-16796 - Nuclear energy - Determination of Gd2O3 content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES) (ISO 16796:2022, IDT)
- SS-ISO-16966 - Nuclear energy - Nuclear fuel technology - Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors (ISO 16966:2013, IDT)
- SS-ISO-1709 - Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing (ISO 1709:2018, IDT)
- SS-ISO-1709-AM1 - Nuclear energy - Fissile materials - Principles of criticality safety in storing, handling and processing (ISO 1709:2018/Amd 1, IDT)
- SS-ISO-18213-1 - Nuclear fuel technology -Tank calibration and volume determination for nuclear materials accountancy - Part 1: Procedural overview (ISO 18213-1:2007, IDT)
- SS-ISO-18213-2 - Nuclear fuel technology -Tank calibration and volume determination for nuclear materials accountancy - Part 2: Data standardization for tank calibration (ISO 18213-2:2007, IDT)
- SS-ISO-18213-3 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 3: Statistical methods (ISO 18213-3:2009, IDT)
- SS-ISO-18213-4 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 4: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, slow bubbling rate (ISO 18213-4:2008, IDT)
- SS-ISO-18213-5 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 5: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, fast bubbling rate (ISO 18213-5:2008, IDT)
- SS-ISO-18213-6 - Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 6: Accurate in-tank determination of liquid density in accountancy tanks equipped with dip tubes (ISO 18213-6:2008, IDT)
- SS-ISO-18256-1 - Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019, IDT)
- SS-ISO-18256-2 - Nuclear fuel technology - Dissolution of plutonium dioxide-containing materials - Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019, IDT)
- SS-ISO-18315 - Nuclear energy - Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis (ISO 18315:2018, IDT)
- SS-ISO-18557 - Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes (ISO 18557:2017, IDT)
- SS-ISO-19017 - Guidance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015, IDT)
- SS-ISO-21238 - Nuclear energy - Nuclear fuel technology - The scaling factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants (ISO 21238:2007, IDT)
- SS-ISO-21391 - Nuclear criticality safety - Geometrical dimensions for subcriticality control - Equipment and layout (ISO 21391:2019, IDT)
- SS-ISO-21483 - Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2 (ISO 21483:2013, IDT)
- SS-ISO-21484 - Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method (ISO 21484:2017, IDT)
- SS-ISO-21847-1 - Nuclear fuel technology - Alpha spectrometry - Part 1: Determination of neptunium in uranium and its compounds (ISO 21847-1:2007, IDT)
- SS-ISO-21847-2 - Nuclear fuel technology - Alpha spectrometry - Part 2: Determination of plutonium in uranium and its compounds (ISO 21847-2:2007, IDT)
- SS-ISO-21847-3 - Nuclear fuel technology - Alpha spectrometry - Part 3: Determination of uranium 232 in uranium and its compounds (ISO 21847-3:2007, IDT)
- SS-ISO-22127 - Dosimetry with radiophotoluminescent glass dosimeters for dosimetry audit in MV X-ray radiotherapy (ISO 22127:2019, IDT)
- SS-ISO-22765 - Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination (ISO 22765:2016, IDT)
- SS-ISO-22875 - Nuclear energy - Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets (ISO 22875:2008, IDT)
- SS-ISO-24459 - Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry (ISO 24459:2021, IDT)
- SS-ISO-26062 - Nuclear technology - Nuclear fuels - Procedures for the measurement of elemental impurities in uranium- and plutonium-based materials by inductively coupled plasma mass spectrometry (ISO 26062:2010, IDT)
- SS-ISO-27467 - Nuclear criticality safety - Analysis of a postulated criticality accident (ISO 27467:2009, IDT)
- SS-ISO-27468 - Nuclear criticality safety - Evaluation of systems containing PWR UOX fuels - Bounding burnup credit approach (ISO 27468:2011, IDT)
- SS-ISO-7097-1 - Nuclear fuel technology - Determination of uranium in solutions, uranium hexafluoride and solids - Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method (ISO 7097-1:2004, IDT)
- SS-ISO-7097-2 - Nuclear fuel technology Determination of uranium in solutions, uranium hexafluoride and solids Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method (ISO 7097-2:2022, IDT)
- SS-ISO-7195 - Nuclear energy Packagings for the transport of uranium hexafluoride (UF6) (ISO 7195:2020, IDT)
- SS-ISO-7476 - Nuclear fuel technology - Determination of uranium in uranyl nitrate solutions of nuclear grade quality - Gravimetric method (ISO 7476:2003, IDT)
- SS-ISO-8298 - Nuclear fuel technology - Determination of milligram amounts of plutonium in nitric acid solutions - Potentiometric titration with potassium dichromate after oxidation by Ce(IV) and reduction by Fe(II) (ISO 8298:2000, IDT)
- SS-ISO-8299 - Nuclear fuel technology - Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry (ISO 8299:2019, IDT)
- SS-ISO-8300 - Nuclear fuel technology - Determination of plutonium content in plutonium dioxide of nuclear grade quality - Gravimetric method (ISO 8300:2013, IDT)
- SS-ISO-8425 - Nuclear fuel technology - Determination of plutonium in pure plutonium nitrate solutions - Gravimetric method (ISO 8425:2013, IDT)
- SS-ISO-9005 - Nuclear energy - Uranium dioxide powder and sintered pellets - Determination of oxygen/uranium atomic ratio by the amperometric method (ISO 9005:2007, IDT)
- SS-ISO-9006 - Uranium metal and uranium dioxide powder and pellets - Determination of nitrogen content - Method using ammonia-sensing electrode
- SS-ISO-9161 - Uranium dioxide powder - Determination of apparent density and tap density (ISO 9161:2019, IDT)
- SS-ISO-9278 - Nuclear energy - Uranium dioxide pellets - Determination of density and volume fraction of open and closed porosity (ISO 9278:2008, IDT)
- SS-ISO-9279 - Uranium dioxide pellets - Determination of density and total porosity - Mercury displacement method
- SS-ISO-9463 - Nuclear energy - Nuclear fuel technology - Determination of plutonium in nitric acid solutions by spectrophotometry (ISO 9463:2019, IDT)
- SS-ISO-9889 - Determination of carbon content in uranium dioxide powder and sintered pellets - Resistance furnacecombustion - Titrimetric/coulometric/infrared absorption method
- SS-ISO-9891 - Determination of carbon content in uranium dioxide powder and sintered pellets - High-frequency induction furnace combustion - Titrimetric/coulometric/infrared absorption methods
- SS-ISO-9892 - Uranium metal, Uranium dioxide powder and pelletsand uranyl nitrate solutions - Determination of fluorine content - Flouride ion selective electrodemethod
- SS-ISO-9894 - Subsampling of uranium hexafluoride in the liquid phase (ISO 9894:1996, IDT)