Тезис

ISO 7097:Part 2 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 does not generate a toxic mixed waste as does the potassium dichromate titration. The method may not be applied to scrap or waste samples until such time as it is qualified by obtaining results statistically equivalent to those obtained by the potassium dichromate method on the same sample types.

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 techniques 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.


Общая информация 

  • Текущий статус
     : Отозвано
    Дата публикации
     : 2004-07
  • Версия
     : 1
  • Технический комитет
     : ISO/TC 85/SC 5 Nuclear installations, processes and technologies
  • ICS
     :
    27.120.30 Fissile materials and nuclear fuel technology

Жизненный цикл

Появились вопросы?

Ознакомьтесь с FAQ

Работа с клиентами
+41 22 749 08 88

Часы работы:
Понедельник – пятница: 09:00-12:00, 14:00-17:00 (UTC+1)

  2. Интернет-магазин
  3. Каталог стандартов
  4. МКС
  5. 27
  6. 27.120
  7. 27.120.30
  8. ISO 7097-2:2004