1 Scope
This document describes an analytical method for the determination of uranium in samples
from pure product materials such as U metal, UO 2 , UO 3 , U 3 O 8 , 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.