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

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

Nuclear energy — Packagings for the transport of uranium hexafluoride (UF6) — Amendment 1: Welded version and new type of valve for 1S and 2S cylinders

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

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)

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

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

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 — High-frequency induction furnace combustion — Titrimetric/coulometric/infrared absorption methods

Subsampling of uranium hexafluoride in the liquid phase

Validation of the strength of reference solutions used for measuring concentrations

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 — Amendment 1: Corrections and clarifications

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

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

Nuclear fuel technology — Controlled-potential coulometric measurement of plutonium

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

Representative sampling of plutonium nitrate solutions for determination of plutonium concentration

Safe transport of radioactive materials — Leakage testing on packages

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

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

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 — Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination

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 2: Data standardization for tank calibration

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 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 2: Dissolution of MOX pellets and powders

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

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

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

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

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

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

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