27.120.30 Fissile materials

BS ISO 7195. Nuclear energy. Packagings for the transport of uranium hexafluoride (UF6)

BS ISO 11482. Statistical guidelines for the estimation of sampling plans for uranium and plutonium oxide powders

BS ISO 16795. Nuclear energy. Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry

BS IEC 63148. Requirements of tracking system for radioactive materials

BS ISO 24459. Determination of Uranium content in samples coming from the Nuclear Fuel cycle by L-absorption Edge Spectrometry

BS ISO 16796. 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)

Nuclear fuel technology. Controlled-potential coulometric assay of plutonium

Nuclear energy. Determination of nitrogen content in UO₂, (U,Gd)O₂ and (U,Pu)O₂ sintered pellets. Inert gas extraction and conductivity detection method

Nuclear fuel technology. Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method

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 Samples containing plutonium in the microgram range and uranium in the milligram range

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 Samples containing plutonium and uranium in the nanogram range and below

Re-sintering test for UO₂, (U,Gd)O₂ and (U,Pu)O₂ pellets