| Standard and/or project under the direct responsibility of ISO/TC 85/SC 5 Secretariat | Stage | ICS |
|---|---|---|
|
ISO 1709:1995 [Withdrawn]
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 | |
|
ISO 2855:1976 [Withdrawn]
Radioactive materials -- Packagings -- Test for contents leakage and radiation leakage
|
95.99 | |
|
ISO 6961:1982 [Withdrawn]
Long-term leach testing of solidified radioactive waste forms
|
95.99 | |
|
ISO 6962:1982 [Withdrawn]
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 | |
|
ISO 7097:1983 [Withdrawn]
Determination of uranium in reactor fuel solutions and in uranium product solutions -- Iron (II) sulfate reduction/potassium dichromate oxidation titrimetric method
|
95.99 | |
|
Nuclear fuel technology -- Determination of uranium in solutions, uranium hexafluoride and solids -- Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
|
90.20 | |
|
Nuclear fuel technology -- Determination of uranium in solutions, uranium hexafluoride and solids -- Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method
|
90.60 | |
|
ISO 7195:1993 [Withdrawn]
Packaging of uranium hexafluoride (UF6) for transport
|
95.99 | |
|
Nuclear energy -- Packaging of uranium hexafluoride (UF6) for transport
|
90.93 | |
|
ISO/DIS 7195 [Deleted]
Nuclear energy -- Packagings for the transport of uranium hexafluoride (UF6)
|
40.98 | |
|
ISO 7476:1990 [Withdrawn]
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
|
90.60 | |
|
ISO 8298:1987 [Withdrawn]
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 | |
|
ISO 8299:1993 [Withdrawn]
Determination of isotopic content and concentration of uranium and plutonium in nitric acid solution -- Mass spectrometric method
|
95.99 | |
|
ISO 8299:2005 [Withdrawn]
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 | |
|
ISO 8300:1987 [Withdrawn]
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 | |
|
ISO 8425:1987 [Withdrawn]
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
|
90.20 | |
|
ISO 9005:1994 [Withdrawn]
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 | |
|
ISO 9161:2004 [Withdrawn]
Uranium dioxide powder -- Determination of apparent density and tap density
|
95.99 | |
|
Uranium dioxide powder -- Determination of apparent density and tap density
|
60.60 | |
|
ISO 9278:1992 [Withdrawn]
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
|
90.20 | |
|
Uranium dioxide pellets -- Determination of density and total porosity -- Mercury displacement method
|
90.93 | |
|
ISO 9463:1990 [Withdrawn]
Nitric acid feed solutions from reprocessing plants -- Spectrophotometric determination of plutonium after oxidation to plutonium(VI)
|
95.99 | |
|
ISO 9463:2009 [Withdrawn]
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 | |
|
ISO 9989:1996 [Withdrawn]
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
|
90.92 | |
|
ISO/DIS 10276 [Under development]
Nuclear energy -- Fuel technology -- Trunnions for packages used to transport radioactive material
|
40.20 | |
|
Validation of the strength of reference solutions used for measuring concentrations
|
90.60 | |
|
ISO 10981:1993 [Withdrawn]
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
|
90.20 | |
|
Nuclear criticality safety -- Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors
|
90.93 | |
|
Nuclear criticality safety -- Emergency preparedness and response
|
90.93 | |
|
Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant
|
90.92 | |
|
ISO/DIS 11482 [Under development]
Statistical guidelines for the estimation of sampling plans for uranium and plutonium oxide powders
|
40.99 | |
|
ISO 11483:1994 [Withdrawn]
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
|
90.93 | |
|
ISO 11597:1995 [Withdrawn]
Verification of samples of uranyl or plutonium nitrate solutions by density measurements
|
95.99 | |
|
ISO 11598:1995 [Withdrawn]
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
|
90.60 | |
|
Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste
|
90.93 | |
|
ISO/WD 11932 [Deleted]
Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste
|
20.98 | |
|
ISO 12183:1995 [Withdrawn]
Controlled-potential coulometric assay of plutonium
|
95.99 | |
|
ISO 12183:2005 [Withdrawn]
Nuclear fuel technology -- Controlled-potential coulometric assay of plutonium
|
95.99 | |
|
Nuclear fuel technology -- Controlled-potential coulometric assay of plutonium
|
60.60 | |
|
ISO 12184:1994 [Withdrawn]
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
|
90.93 | |
|
Nuclear energy -- Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets -- Inert gas extraction and conductivity detection method
|
60.60 | |
|
ISO 12800:2003 [Withdrawn]
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
|
60.60 | |
|
Representative sampling of plutonium nitrate solutions for determination of plutonium concentration
|
90.60 | |
|
ISO 12807:1996 [Withdrawn]
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
|
90.93 | |
|
Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants -- Combined method using K-absorption edge and X-ray fluorescence spectrometry
|
90.93 | |
|
ISO 13465:1997 [Withdrawn]
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
|
90.93 | |
|
ISO 14850-1:2004 [Withdrawn]
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
|
90.20 | |
|
ISO 15366:1999 [Withdrawn]
Nuclear energy -- Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and dilution analysis by solvent chromatography
|
95.99 | |
|
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
|
60.60 | |
|
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
|
60.60 | |
|
Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets
|
60.60 | |
|
Nuclear energy -- Isotopic analysis of uranium hexafluoride -- Double-standard gas-source mass spectrometric method
|
90.20 | |
|
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
|
60.60 | |
|
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 | |
|
ISO 16793:2005 [Withdrawn]
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
|
90.93 | |
|
Nuclear energy -- Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry
|
90.92 | |
|
ISO/DIS 16795 [Under development]
Nuclear energy -- Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry
|
40.00 | |
|
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)
|
90.60 | |
|
Nuclear energy -- Soxhlet-mode chemical durability test -- Application to vitrified matrixes for high-level radioactive waste
|
90.20 | |
|
Nuclear energy -- Nuclear fuel technology -- Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
|
60.60 | |
|
Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 1: Procedural overview
|
90.92 | |
|
ISO/DIS 18213-1 [Under development]
Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 1: Procedural overview
|
40.99 | |
|
Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 2: Data standardization for tank calibration
|
90.92 | |
|
ISO/DIS 18213-2 [Under development]
Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 2: Data standardization for tank calibration
|
40.99 | |
|
Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 3: Statistical methods
|
90.93 | |
|
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
|
90.92 | |
|
ISO/DIS 18213-4 [Under development]
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
|
40.99 | |
|
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
|
90.92 | |
|
ISO/DIS 18213-5 [Under development]
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
|
40.99 | |
|
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
|
90.92 | |
|
ISO/DIS 18213-6 [Under development]
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
|
40.99 | |
|
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
|
60.60 | |
|
Guidance for gamma spectrometry measurement of radioactive waste
|
60.60 | |
|
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
|
90.93 | |
|
ISO/DIS 21391 [Under development]
Nuclear criticality safety -- Geometrical nuclear criticality safety dimensions
|
40.99 | |
|
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2
|
90.20 | |
|
ISO 21484:2008 [Withdrawn]
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
|
60.60 | |
|
(U, Pu)O2 Powders and sintered pellets -- Determination of chlorine and fluorine
|
60.60 | |
|
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
|
90.20 | |
|
Nuclear fuel technology -- Alpha spectrometry -- Part 1: Determination of neptunium in uranium and its compounds
|
90.92 | |
|
ISO 21847-1:2007/CD Amd 1 [Deleted]
|
30.98 | |
|
ISO/CD 21847-1 [Under development]
Nuclear fuel technology -- Alpha spectrometry -- Part 1: Determination of neptunium in uranium and its compounds
|
30.00 | |
|
Nuclear fuel technology -- Alpha spectrometry -- Part 2: Determination of plutonium in uranium and its compounds
|
90.92 | |
|
ISO 21847-2:2007/CD Amd 1 [Deleted]
|
30.98 | |
|
ISO/CD 21847-2 [Under development]
Nuclear fuel technology -- Alpha spectrometry -- Part 2: Determination of plutonium in uranium and its compounds
|
30.00 | |
|
Nuclear fuel technology -- Alpha spectrometry -- Part 3: Determination of uranium 232 in uranium and its compounds
|
90.92 | |
|
ISO 21847-3:2007/CD Amd 1 [Deleted]
|
30.98 | |
|
ISO/CD 21847-3 [Under development]
Nuclear fuel technology -- Alpha spectrometry -- Part 3: Determination of uranium 232 in uranium and its compounds
|
30.00 | |
|
Nuclear fuel technology -- Sintered (U,Pu)O2 pellets -- Guidance for ceramographic preparation for microstructure examination
|
60.60 | |
|
ISO 22875:2008 [Withdrawn]
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
|
60.60 | |
|
ISO/DIS 22946 [Under development]
Nuclear criticality safety -- Solid waste (excluding irradiated and non-irradiated fuel)
|
40.20 | |
|
ISO/CD 23133 [Under development]
Nuclear Criticality Safety -- Criticality Safety Training for Operations
|
30.00 | |
|
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
|
90.93 |
No matching records found