ISO 7097-2:2022
Current
The latest, up-to-date edition.
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method
Hardcopy , PDF , PDF 3 Users , PDF 5 Users , PDF 9 Users , Hardcopy, PDF, PDF 3 Users, PDF 5 Users, PDF 9 Users
English, French
11-25-2022
This document describes an analytical method for the determination of uranium in samples from pure product materials such as Umetal, 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 ISO7097-1.
Important note : All end users must be registered with an Account prior to user licenses being assigned.Access your standards online with a subscription
Features
-
Simple online access to standards, technical information and regulations.
-
Critical updates of standards and customisable alerts and notifications.
-
Multi-user online standards collection: secure, flexible and cost effective.