ISO 7097-2:2022
p
ISO 7097-2:2022
78873
недоступно на русском языке

Текущий статус : Опубликовано

ru
Формат Язык
std 1 96 PDF + ePub
std 2 96 Бумажный
  • CHF96
Пересчитать швейцарские франки (CHF) в ваша валюта

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.

Preview 

Вы можете ознакомиться с данным стандартом в нашей онлайн-библиотеке (OBP)

Общая информация

  •  : Опубликовано
     : 2022-11
    : Опубликование международного стандарта [60.60]
  •  : 2
  • ISO/TC 85/SC 5
    27.120.30 
  • RSS обновления

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)