International Standard
ISO 7097-2:2022
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method
Reference number
ISO 7097-2:2022
Версия 2
2022-11
© ISO 2024
International Standard
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Опубликовано (Версия 2, 2022)

ISO 7097-2:2022

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Тезис

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.

Общая информация

  • Текущий статус
     : Опубликовано
    Дата публикации
     : 2022-11
    Этап
    : Опубликование международного стандарта [60.60]
  • Версия
     : 2
  • Технический комитет :
    ISO/TC 85/SC 5
    ICS :
    27.120.30 
  • RSS обновления

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  2. Интернет-магазин
  3. Каталог стандартов
  4. МКС
  5. 27
  6. 27.120
  7. 27.120.30
  8. ISO 7097-2:2022