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DIN 25709:1995-10
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DIN 25709:1995-10
Post-sintering test for UO2 and UO2/Gd2O3 nuclear fuel pelletsMore info
The in-pile density increase of ceramic nuclear fuel tablets after a burn-up of ca. 10 GWd/HU depends on various parameters such as pore size and structure, grain size etc. It is determined by a pre-heating density measurement, followed by another such measurement after the heat treatment under defined conditions. From the difference of both measurements, the post-sintering effect is determined.
| Author | DIN |
|---|---|
| Editor | DIN |
| Document type | Standard |
| Format | File |
| expiration_de_validite | 2010-05-31 |
| ICS | 27.120.30 : Fissile materials and nuclear fuel technology
|
| Number of pages | 2 |
| Replace | DIN 25709 (1994-05) |
| Year | 1990 |
| Document history | DIN 25709 (1995-10) |
| Country | Germany |
| Keyword | 25709 |