SS-ISO-7097-2 › Nuclear fuel technology Determination of uranium in solutions, uranium hexafluoride and solids Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method (ISO 7097-2:2022, IDT)
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This document describes an analytical method for the determination of uranium in samples from pure product materials such as U metal, UO2, UO3, U3O8, uranyl nitrate hexahydrate and uranium hexafluoride from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability. This method can be used directly for the analysis of most uranium and uranium oxide nuclear reactor fuels, either irradiated or un-irradiated, and of uranium nitrate product solutions. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere, and other elements which could cause interference are not normally present in sufficient quantity to affect the result significantly. The method recommends that an aliquot of sample is weighed and that a mass titration is used, in order to obtain improved precision and accuracy. This does not preclude the use of alternative techniques which could give equivalent performance. The use of automatic device(s) in the performance of some critical steps of the method has some advantages, mainly in the case of routine analysis. This method does not generate a toxic mixed waste as does the potassium dichromate titration in ISO 7097-1.
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Designation Name
SS-ISO 7097-2:2022
Revision Level
2022 EDITION
Status
Current
Publication Date
Nov. 29, 2022
Language(s)
English
Page Count
28
International Equivalent
ISO 7097-2:2022(IDT)