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DIN 25701:1991-09

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DIN 25701:1991-09

Determination of the solubility of plutonium from unirradiated mixed oxide nuclear fuels in nitric acid

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This standard specifies a method for the determination of the fraction of plutonium in unirradiated mixed oxide nuclear fuels, which is soluble in nitric acid. About 20 g mixed oxide are required. The results permit predictions about the solubility of mixed oxide nuclear fuels during their reprocessing.

Author DIN
Editor DIN
Document type Standard
Format File
ICS 27.120.30 : Fissile materials and nuclear fuel technology
Number of pages 2
Replace DIN 25701 (1989-10)
Cross references ISO 12184 (1994-08), IDT
Year 1990
Document history DIN 25701 (1991-09)
Country Germany
Keyword 25701