DIN 25463-2
Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors
| Organization: | DIN |
| Publication Date: | 1 February 2014 |
| Status: | active |
| Page Count: | 45 |
| ICS Code (Fissile materials and nuclear fuel technology): | 27.120.30 |
scope:
This document shall be used for calculating the decay power of uranium-plutonium mixed-oxide nuclear fuel in pressurized water reactors (PWRs).
The calculation instructions apply to
- decay times of 0 s to 2 ⋅ 109 s (approximately 60 years),
- plutonium quality in new fuel ranging from 50 % to 80 %,
- Pufiss fraction in new fuel ranging from 1,8 % to 7,5 %,
- effective moderation ratios of 1,80 to 2,40,
- uranium carrier material with a 235U fraction of up to 0,72 % and
- burn-up rates of heavy metals ranging from 0 MWd/kg to 60 MWd/kg,
whereby the respective combination of plutonium quality and Pufiss fraction shall be inside the parallelogram defined by the four corners (Pufiss fraction/plutonium quality) = (4 %/50 %); (1,8 %/80 %); (5,3 %/80 %); (7,5 %/50 %) (see Figure 1).
If the calculations are carried out for conditions outside of the above value range, users may apply their own calculation methods and databases, provided that the validity of these can be proved.
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