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); German version EN ISO 15366-1:2016— 16 стр.
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); German version EN ISO 15366-2:2016— 17 стр.
Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O<(Index)2> (ISO 21483:2013); German version EN ISO 21483:2017— 11 стр.
Nuclear fuel technology - Guidelines for ceramographic preparation of UO<(Index)2> sintered pellets for microstructure examination (ISO 16793:2018); English version EN ISO 16793:2021— 14 стр.
Nuclear energy - Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd<(Index)2>O<(Index)3> content in gadolinium fuel pellets by measurements of uranium and gadolinium elements (ISO 16424:2012); German version EN ISO 16424:2017— 21 стр.
Nuclear energy - Determination of total hydrogen content in PuO<(Index)2> and UO<(Index)2> powders and UO<(Index)2>, (U,Gd)O<(Index)2> and (U,Pu)O<(Index)2> sintered pellets - Inert gas extraction and conductivity detection method (ISO 15651:2015); German version EN ISO 15651:2017— 11 стр.
Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors— 45 стр.
Criticality safety in processing and handling of fissile materials - Part 8: Criticality data of uranyl nitrate (100% uranium 235) light-water mixture— 8 стр.
