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Nuclear energy - Fuel technology - Trunnion systems for packages used to transport radioactive material (ISO 10276:2019)
60.60 Standard published
Nuclear fuel technology - Controlled-potential coulometric measurement of plutonium (ISO 12183:2024)
60.60 Standard published
Safe transport of radioactive materials - Leakage testing on packages (ISO 12807:2018)
60.60 Standard published
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)
60.60 Standard published
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)
60.60 Standard published
Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets (ISO 15646:2014)
60.60 Standard published
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)
60.60 Standard published
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)
60.60 Standard published
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)
60.60 Standard published
Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes (ISO 18557:2017)
60.60 Standard published
Guidance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015)
60.60 Standard published
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2 (ISO 21483:2013)
60.60 Standard published
Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry (ISO 24459:2021)
60.60 Standard published
Nuclear energy - Determination of Gd2O3 content in pellets containing uranium oxide by X-ray fluorescence spectrometry (ISO 16795:2024)
40.20 DIS ballot initiated: 12 weeks
Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination (ISO 22765:2025)
40.20 DIS ballot initiated: 12 weeks
Nuclear energy — Fuel technology — Trunnion systems for packages used to transport radioactive material
90.93 Standard confirmed
Validation of the strength of reference solutions used for measuring concentrations
90.93 Standard confirmed
Nuclear fuel technology — Determination of uranium in reprocessing-plant dissolver solution — Liquid chromatography method
90.92 Standard to be revised
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