2. Getting involved
3. Standards Committees
4. NMP

DIN Standards Committee Materials Testing

Abstract

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.

Begin

2026-02-12

WI

00430158

Planned document number

DIN EN ISO 7097-2

Project number

06237072

Responsible national committee

NA 062-07 FBR - Board of the Technical Department Radiation protection, nuclear technology and fusion technology  

Responsible european committee

CEN/TC 430 - Nuclear energy, nuclear technologies, and radiological protection  

Responsible international committee

ISO/TC 85/SC 5/WG 1 - Analytical methodology in the nuclear fuel cycle  

draft standard

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); English version prEN ISO 7097-2:2026
2026-05
Order from DIN Media