| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1729855 | Annals of Nuclear Energy | 2009 | 5 Pages |
Abstract
The ATWS transient “Loss of main feed water supply” in a generic four-loop PWR at the nominal power of 3750 MW was analyzed using the coupled code system DYN3D/ATHLET. A variation of the MOX-fuel-assembly portion in the core has an effect on the reactivity coefficients of the fuel temperature and the moderator density. These two parameters mainly influence the behaviour of the coolant pressure, which is safety-relevant. It has been demonstrated that the pressure maximum decreases with an increasing portion of MOX. For all core loadings considered, both primary-circuit mechanical integrity and sufficient core cooling are guaranteed.
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Authors
S. Kliem, S. Mittag, U. Rohde, F.-P. Weiß,