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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 |