ISO 7097-1:2004
2004-07
Abstract
ISO 7097-1:2004 describes an analytical method for the determination of uranium in pure product material samples such as U metal, UO2, UO3, uranyl nitrate hexahydrate, uranium hexafluoride and U3O8 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 unirradiated, 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 any alternative technique which could give equivalent performance. As the performance of some steps of the method is critical, the use of some automatic device has some advantages, mainly in the case of routine analysis.
General information
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Status: PublishedPublication date: 2004-07Stage: International Standard to be revised [90.92]
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Edition: 1Number of pages: 14
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Technical Committee :ISO/TC 85/SC 5ICS :27.120.30
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Next version under development
ISO/DIS 7097-1
ISO/DIS 7097-1
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids
Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
Life cycle
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Previously
WithdrawnISO 7097:1983
WithdrawnISO 9989:1996
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Now
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Will be replaced by
Under developmentISO/DIS 7097-1