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DIN 25711:1996-06

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DIN 25711:1996-06

Determination of the 232U isotopic content in uranium containing nuclear fuel solutions by ? spectrometry

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This document describes a method for the determination of the 232U isotopic content in solutions of UO2F2 or UO2(NO3) to the level of 5 × 10-11. Uranium oxides and UF6 can be transferred into solutions and analyzed by a simple treatment. It is used for recycled uranium, or uranium containing recycled uranium.

Author DIN
Editor DIN
Document type Standard
Format File
ICS 27.120.30 : Fissile materials and nuclear fuel technology
Number of pages 3
Replace DIN 25711 (1995-04)
Year 1990
Document history DIN 25711 (1996-06)
Country Germany
Keyword 25711