Фильтр :
Стандарт и/или проект находящийся в компетенции ISO/TC 85/SC 5 Секретариата Этап ICS
Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing
95.99
Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing
60.60
Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing — Amendment 1: Methods of control and safety equipment
60.60
Radioactive materials — Packagings — Test for contents leakage and radiation leakage
95.99
Preparation of Plutonium and Uranium spikes for Isotope Dilution Mass Spectrometry (IDMS)
20.00
Long-term leach testing of solidified radioactive waste forms
95.99
Standard method for testing the long term alpha irradiation stability of solidified high-level radioactive waste forms
95.99
Nuclear energy — Standard method for testing the long-term alpha irradiation stability of matrices for solidification of high-level radioactive waste
90.93
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
90.92
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
20.00
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method
95.99
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method
60.60
Determination of uranium in reactor fuel solutions and in uranium product solutions — Iron (II) sulfate reduction/potassium dichromate oxidation titrimetric method
95.99
Packaging of uranium hexafluoride (UF6) for transport
95.99
Nuclear energy — Packaging of uranium hexafluoride (UF6) for transport
95.99
Nuclear energy — Packagings for the transport of uranium hexafluoride (UF6)
60.60
Determination of uranium in uranyl nitrate solutions of nuclear grade quality — Gravimetric method
95.99
Nuclear fuel technology — Determination of uranium in uranyl nitrate solutions of nuclear grade quality — Gravimetric method
90.93
Nuclear energy — Performance and testing requirements for criticality detection and alarm systems
90.92
Nuclear criticality safety — Use of criticality accident alarm systems for operations
40.60
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
95.99
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)
90.93
Determination of isotopic content and concentration of uranium and plutonium in nitric acid solution — Mass spectrometric method
95.99
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
95.99
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
60.60
Determination of plutonium content in plutonium dioxide (PuO2) of nuclear grade quality — Gravimetric method
95.99
Nuclear fuel technology — Determination of plutonium content in plutonium dioxide of nuclear grade quality — Gravimetric method
90.93
Application of Knowledge Management to Radioactive Waste Management — Part 1: Overarching
20.00
Application of Knowledge Management to Radioactive Waste Management — Part 2: Vision and strategy
20.00
Application of Knowledge Management to Radioactive Waste Management — Part 3: Process
20.00
Application of Knowledge Management to Radioactive Waste Management — Part 4: People
20.00
Application of Knowledge Management to Radioactive Waste Management — Part 5: Tools and technology
20.00
Application of Knowledge Management to Radioactive Waste Management — Part 6: Implementation
20.00
Application of Knowledge Management to Radioactive Waste Management
20.98
Determination of plutonium in pure plutonium nitrate solutions — Gravimetric method
95.99
Nuclear fuel technology — Determination of plutonium in pure plutonium nitrate solutions — Gravimetric method
90.93
Decommissioning of medical cyclotron
30.60
Uranium dioxide powder and sintered pellets — Determination of oxygen/uranium atomic ratio — Amperometric method
95.99
Nuclear energy — Uranium dioxide powder and sintered pellets — Determination of oxygen/uranium atomic ratio by the amperometric method
90.93
Uranium metal and uranium dioxide powder and pellets — Determination of nitrogen content — Method using ammonia-sensing electrode
90.93
Uranium dioxide powder — Determination of apparent density and tap density
95.99
Uranium dioxide powder — Determination of apparent density and tap density
60.60
Uranium dioxide pellets — Determination of density and amount of open and closed porosity — Boiling water method and penetration immersion method
95.99
Nuclear energy - Uranium dioxide pellets — Determination of density and volume fraction of open and closed porosity
90.93
Uranium dioxide pellets — Determination of density and total porosity — Mercury displacement method
90.93
Nitric acid feed solutions from reprocessing plants — Spectrophotometric determination of plutonium after oxidation to plutonium(VI)
95.99
Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry
95.99
Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry
60.60
Determination of carbon content in uranium dioxide powder and sintered pellets — Resistance furnace combustion — Titrimetric/coulometric/infrared absorbtion method
90.93
Determination of carbon content in uranium dioxide powder and sintered pellets — High-frequency induction furnace combustion — Titrimetric/coulometric/infrared absorption methods
90.93
Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions — Determination of fluorine content — Fluoride ion selective electrode method
90.93
Subsampling of uranium hexafluoride in the liquid phase
90.93
Determination of uranium in uranium dioxide powder and pellets — Iron(II) sulfate reduction/potassium dichromate oxidation titrimetric method
95.99
Nuclear energy — Fuel technology — Trunnions for packages used to transport radioactive material
95.99
Nuclear energy — Fuel technology — Trunnion systems for packages used to transport radioactive material
60.60
Validation of the strength of reference solutions used for measuring concentrations
90.93
Determination of uranium in reprocessing plants dissolver solution — Liquid chromatography method
95.99
Nuclear fuel technology — Determination of uranium in reprocessing-plant dissolver solution — Liquid chromatography method
90.60
Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors
90.93
Nuclear criticality safety — Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors — Amendment 1: Corrections and clarifications
60.00
Nuclear criticality safety — Emergency preparedness and response
90.93
Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant
90.60
Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry
95.99
Nuclear fuel technology — Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry
90.60
Verification of samples of uranyl or plutonium nitrate solutions by density measurements
95.99
Requirements for representative sampling of uranyl nitrate solutions for the determination of uranium concentration
95.99
Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste
90.93
Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste
90.93
Controlled-potential coulometric assay of plutonium
95.99
Nuclear fuel technology — Controlled-potential coulometric assay of plutonium
95.99
Nuclear fuel technology — Controlled-potential coulometric assay of plutonium
90.92
Nuclear fuel technology — Controlled-potential coulometric assay of plutonium
20.00
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O2
95.99
Nuclear fuel technology — Uranium dioxide powder and pellets — Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction
90.60
Nuclear energy — Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets — Inert gas extraction and conductivity detection method
90.93
Nuclear fuel technology — Guide to the measurement of the specific surface area of uranium oxide powders by the BET method
95.99
Nuclear fuel technology — Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method
90.93
Representative sampling of plutonium nitrate solutions for determination of plutonium concentration
90.93
Safe transport of radioactive materials — Leakage testing on packages
95.99
Safe transport of radioactive materials — Leakage testing on packages
60.60
Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel — Guidelines to help in the definition of a product specification
90.20
Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants — Combined method using K-absorption edge and X-ray fluorescence spectrometry
90.60
Determination of neptunium in nitric acid solutions by molecular absorption spectrophotometry
95.99
Nuclear energy — Nuclear fuel technology — Determination of neptunium in nitric acid solutions by spectrophotometry
90.60
Nuclear energy — Waste-packages activity measurement — Part 1: High-resolution gamma spectrometry in integral mode with open geometry
95.99
Nuclear fuel technology — Administrative criteria related to nuclear criticality safety
90.93
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
90.93
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
90.93
Nuclear energy — Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and dilution analysis by solvent chromatography
95.99
Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets
90.60
Nuclear energy — Isotopic analysis of uranium hexafluoride — Double-standard gas-source mass spectrometric method
90.93
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
90.93
Nuclear criticality safety — Estimation of the number of fissions of a postulated criticality accident
90.93
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
90.93
Nuclear fuel technology — Guide for ceramographic preparation of UO2 sintered pellets for microstructure examination
95.99
Nuclear fuel technology — Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination
60.60
Nuclear energy — Determination of carbon compounds and fluorides in uranium hexafluoride infrared spectrometry
90.60
Nuclear energy — Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry
90.92
Nuclear energy — Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry
30.99
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)
95.99
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)
60.60
Nuclear energy — Soxhlet-mode chemical durability test — Application to vitrified matrixes for high-level radioactive waste
90.93
Nuclear energy — Nuclear fuel technology — Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
90.93
Nuclear fuel technology — Tank calibration and volume determination for nuclear materials accountancy — Part 1: Procedural overview
90.93
Nuclear fuel technology — Tank calibration and volume determination for nuclear materials accountancy — Part 2: Data standardization for tank calibration
90.93
Nuclear fuel technology — Tank calibration and volume determination for nuclear materials accountancy — Part 3: Statistical methods
90.60
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
90.93
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
90.93
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
90.93
Nuclear fuel technology — Dissolution of plutonium dioxide-containing materials — Part 1: Dissolution of plutonium dioxide powders
60.60
Nuclear fuel technology — Dissolution of plutonium dioxide-containing materials — Part 2: Dissolution of MOX pellets and powders
60.60
Nuclear energy — Guidance to the evaluation of measurement uncertainties of impurity in uranium solution by linear regression analysis
60.60
Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
90.20
Guidance for gamma spectrometry measurement of radioactive waste
90.93
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
90.20
Nuclear criticality safety — Geometrical dimensions for subcriticality control — Equipment and layout
60.60
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
90.93
Nuclear fuel technology — Determination of the O/M ratio in MOX pellets — Gravimetric method
95.99
Nuclear Energy — Fuel technology — Determination of the O/M ratio in MOX pellets by the gravimetric method
90.60
(U, Pu)O2 Powders and sintered pellets — Determination of chlorine and fluorine
90.93
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
90.60
Nuclear fuel technology — Alpha spectrometry — Part 1: Determination of neptunium in uranium and its compounds
90.93
Nuclear fuel technology — Alpha spectrometry — Part 2: Determination of plutonium in uranium and its compounds
90.93
Nuclear fuel technology — Alpha spectrometry — Part 3: Determination of uranium 232 in uranium and its compounds
90.93
Nuclear fuel technology — Sintered (U,Pu)O2 pellets — Guidance for ceramographic preparation for microstructure examination
90.92
Nuclear fuel technology — Sintered (U,Pu)O2 pellets — Guidance for ceramographic preparation for microstructure examination
20.00
Nuclear energy — Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets
95.99
Nuclear energy — Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets
90.60
Nuclear criticality safety — Solid waste excluding irradiated and non-irradiated nuclear fuel
60.60
Nuclear criticality safety — Nuclear criticality safety training for operations
60.60
Management of radioactive waste from nuclear facilities — Part 1: General principles, objectives and practical approaches
50.20
Nuclear energy — Nuclear fuel technology — Methodologies for radioactivity characterization of Very Low Level Waste (VLLW) produced by nuclear facilities
40.00
Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry
60.60
Nuclear technology — Nuclear fuels — Procedures for the measurement of elemental impurities in uranium- and plutonium-based materials by inductively coupled plasma mass spectrometry
90.93
Nuclear criticality safety — Analysis of a postulated criticality accident
90.93
Nuclear criticality safety — Evaluation of systems containing PWR UOX fuels — Bounding burnup credit approach
90.60

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