No products
View larger
New product
This standard is to be applied to the calculation of the decay power of mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors. Calculation instructions and data sets are made available to the user enabling him to calculate the decay power for the given combination of plutonium portion in the fuel element, the plutonium quality and the moderating ratio.
| Author | DIN |
|---|---|
| Editor | DIN |
| Document type | Standard |
| Format | File |
| ICS | 27.120.30 : Fissile materials and nuclear fuel technology
|
| Number of pages | 45 |
| Replace | DIN 25463-2 (2008-03) |
| Year | 2014 |
| Document history | DIN 25463-2 (2014-02) |
| Country | Germany |
| Keyword | DIN 25463;25463 |