Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing

Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing

Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing — Amendment 1: Methods of control and safety equipment

Radioactive materials — Packagings — Test for contents leakage and radiation leakage

Nuclear fuel technology — Preparation of spikes for isotope dilution mass spectrometry (IDMS)

Long-term leach testing of solidified radioactive waste forms

Standard method for testing the long term alpha irradiation stability of solidified high-level radioactive waste forms

Nuclear energy — Standard method for testing the long-term alpha irradiation stability of matrices for solidification of high-level radioactive waste

Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method

Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method

Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method

Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method

Determination of uranium in reactor fuel solutions and in uranium product solutions — Iron (II) sulfate reduction/potassium dichromate oxidation titrimetric method

Packaging of uranium hexafluoride (UF6) for transport

Nuclear energy — Packaging of uranium hexafluoride (UF6) for transport

Nuclear energy — Packagings for the transport of uranium hexafluoride (UF6)

Nuclear energy — Packagings for the transport of uranium hexafluoride (UF6) — Amendment 1

Determination of uranium in uranyl nitrate solutions of nuclear grade quality — Gravimetric method

Nuclear fuel technology — Determination of uranium in uranyl nitrate solutions of nuclear grade quality — Gravimetric method

Nuclear energy — Performance and testing requirements for criticality detection and alarm systems

Nuclear criticality safety — Use of criticality accident alarm systems for operations

Determination of plutonium in nitric acid solutions — Method by oxidation by cerium(IV), reduction by iron(II) ammonium sulfate and amperometric back-titration with potassium dichromate

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)

Determination of isotopic content and concentration of uranium and plutonium in nitric acid solution — Mass spectrometric method

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

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

Determination of plutonium content in plutonium dioxide (PuO2) of nuclear grade quality — Gravimetric method

Nuclear fuel technology — Determination of plutonium content in plutonium dioxide of nuclear grade quality — Gravimetric method

Guidelines for managing knowledge to support radioactive waste management — Part 1: Purpose and Overview of ISO 8345 and Introduction to Knowledge Management

Guidelines for managing knowledge to support radioactive waste management — Part 2: Vision and strategy

Determination of plutonium in pure plutonium nitrate solutions — Gravimetric method

Nuclear fuel technology — Determination of plutonium in pure plutonium nitrate solutions — Gravimetric method

Decommissioning of medical cyclotron

Uranium dioxide powder and sintered pellets — Determination of oxygen/uranium atomic ratio — Amperometric method

Nuclear energy — Uranium dioxide powder and sintered pellets — Determination of oxygen/uranium atomic ratio by the amperometric method

Uranium metal and uranium dioxide powder and pellets — Determination of nitrogen content — Method using ammonia-sensing electrode

Uranium dioxide powder — Determination of apparent density and tap density

Uranium dioxide powder — Determination of apparent density and tap density

Uranium dioxide pellets — Determination of density and amount of open and closed porosity — Boiling water method and penetration immersion method

Nuclear energy - Uranium dioxide pellets — Determination of density and volume fraction of open and closed porosity

Uranium dioxide pellets — Determination of density and total porosity — Mercury displacement method

Nitric acid feed solutions from reprocessing plants — Spectrophotometric determination of plutonium after oxidation to plutonium(VI)

Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry

Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry

Determination of carbon content in uranium dioxide powder and sintered pellets — Resistance furnace combustion — Titrimetric/coulometric/infrared absorbtion method

Determination of carbon content in uranium dioxide powder and sintered pellets — High-frequency induction furnace combustion — Titrimetric/coulometric/infrared absorption methods

Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions — Determination of fluorine content — Fluoride ion selective electrode method

Subsampling of uranium hexafluoride in the liquid phase

Determination of uranium in uranium dioxide powder and pellets — Iron(II) sulfate reduction/potassium dichromate oxidation titrimetric method

Nuclear energy — Fuel technology — Trunnions for packages used to transport radioactive material

Nuclear energy — Fuel technology — Trunnion systems for packages used to transport radioactive material

Validation of the strength of reference solutions used for measuring concentrations

Determination of uranium in reprocessing plants dissolver solution — Liquid chromatography method

Nuclear fuel technology — Determination of uranium in reprocessing-plant dissolver solution — Liquid chromatography method

Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors

Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors — Amendment 1: Corrections and clarifications

Nuclear criticality safety — Emergency preparedness and response

Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant

Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry

Nuclear fuel technology — Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry

Verification of samples of uranyl or plutonium nitrate solutions by density measurements

Requirements for representative sampling of uranyl nitrate solutions for the determination of uranium concentration

Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste

Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste

Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste

Controlled-potential coulometric assay of plutonium

Nuclear fuel technology — Controlled-potential coulometric assay of plutonium

Nuclear fuel technology — Controlled-potential coulometric assay of plutonium

Nuclear fuel technology — Controlled-potential coulometric measurement of plutonium

Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O2

Nuclear fuel technology — Uranium dioxide powder and pellets — Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction

Nuclear energy — Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets — Inert gas extraction and conductivity detection method

Nuclear fuel technology — Guide to the measurement of the specific surface area of uranium oxide powders by the BET method

Nuclear fuel technology — Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method

Representative sampling of plutonium nitrate solutions for determination of plutonium concentration

Safe transport of radioactive materials — Leakage testing on packages

Safe transport of radioactive materials — Leakage testing on packages

Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel — Guidelines to help in the definition of a product specification

Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants — Combined method using K-absorption edge and X-ray fluorescence spectrometry

Determination of neptunium in nitric acid solutions by molecular absorption spectrophotometry

Nuclear energy — Nuclear fuel technology — Determination of neptunium in nitric acid solutions by spectrophotometry

Nuclear energy — Nuclear fuel technology — Determination of neptunium in nitric acid solutions by spectrophotometry

Nuclear energy — Waste-packages activity measurement — Part 1: High-resolution gamma spectrometry in integral mode with open geometry

Nuclear fuel technology — Administrative criteria related to nuclear criticality safety

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

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

Nuclear energy — Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and dilution analysis by solvent chromatography

Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets

Nuclear energy — Isotopic analysis of uranium hexafluoride — Double-standard gas-source mass spectrometric method

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

Nuclear criticality safety — Estimation of the number of fissions of a postulated criticality accident

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

Nuclear fuel technology — Guide for ceramographic preparation of UO2 sintered pellets for microstructure examination

Nuclear fuel technology — Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination

Nuclear energy — Determination of carbon compounds and fluorides in uranium hexafluoride infrared spectrometry

Nuclear energy — Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry

Nuclear energy — Determination of Gd2O3 content in pellets containing uranium oxide by X-ray fluorescence spectrometry

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)

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)

Nuclear energy — Soxhlet-mode chemical durability test — Application to vitrified matrixes for high-level radioactive waste

Nuclear energy — Nuclear fuel technology — Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors

Nuclear fuel technology — Tank calibration and volume determination for nuclear materials accountancy — Part 1: Procedural overview

Nuclear fuel technology — Tank calibration and volume determination for nuclear materials accountancy — Part 2: Data standardization for tank calibration

Nuclear fuel technology — Tank calibration and volume determination for nuclear materials accountancy — Part 3: Statistical methods

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

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

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

Nuclear fuel technology — Dissolution of plutonium dioxide-containing materials — Part 1: Dissolution of plutonium dioxide powders

Nuclear fuel technology — Dissolution of plutonium dioxide-containing materials — Part 2: Dissolution of MOX pellets and powders

Nuclear energy — Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis

Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes

Guidance for gamma spectrometry measurement of radioactive waste

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

Nuclear criticality safety — Geometrical dimensions for subcriticality control — Equipment and layout

Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2

Nuclear fuel technology — Determination of the O/M ratio in MOX pellets — Gravimetric method

Nuclear Energy — Fuel technology — Determination of the O/M ratio in MOX pellets by the gravimetric method

(U, Pu)O2 Powders and sintered pellets — Determination of chlorine and fluorine

Determination of carbon content of UO2, (U, Gd)O2 and (U, Pu)O2 powders and sintered pellets — Combustion in a high-frequency induction furnace — Infrared absorption spectrometry

Nuclear fuel technology — Alpha spectrometry — Part 1: Determination of neptunium in uranium and its compounds

Nuclear fuel technology — Alpha spectrometry — Part 2: Determination of plutonium in uranium and its compounds

Nuclear fuel technology — Alpha spectrometry — Part 3: Determination of uranium 232 in uranium and its compounds

Nuclear fuel technology — Sintered (U,Pu)O2 pellets — Guidance for ceramographic preparation for microstructure examination

Nuclear fuel technology — Sintered (U,Pu)O2 pellets — Guidance for ceramographic preparation for microstructure examination

Nuclear energy — Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets

Nuclear energy — Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets

Nuclear criticality safety — Solid waste excluding irradiated and non-irradiated nuclear fuel

Nuclear criticality safety — Nuclear criticality safety training for operations

Test of buffer material under coupled thermo-hydro-mechanical conditions for geological disposal of high-level radioactive waste — Part 1: Swelling pressure test

Management of radioactive waste from nuclear facilities — Part 1: General principles, objectives and practical approaches

Nuclear energy — Nuclear fuel technology — Methodologies for radioactivity characterization of very low-level waste (VLLW) generated by nuclear facilities

Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry

Nuclear technology — Nuclear fuels — Procedures for the measurement of elemental impurities in uranium- and plutonium-based materials by inductively coupled plasma mass spectrometry

Nuclear criticality safety — Analysis of a postulated criticality accident

Nuclear criticality safety — Evaluation of systems containing PWR UOX fuels — Bounding burnup credit approach