ATWS analysis for PWR using the coupled code system DYN3D/ATHLET
ATWS analysis for PWR using the coupled code system DYN3D/ATHLET
Kliem, S.; Mittag, S.; Rohde, U.; Weiß, F.-P.
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.
Keywords: reactor safety; MOX, reactivity; temperature-feedback; thermal-hydraulics; transient
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Annals of Nuclear Energy 36(2009), 1230-1234
DOI: 10.1016/j.anucene.2009.04.001
Cited 13 times in Scopus
Permalink: https://www.hzdr.de/publications/Publ-12265