![]() The analysis of the thermal-hydraulic transient phenomena and the core degradation phenomena is therefore here presented. This activity has been performed focusing specifically on the in-vessel phenomenology that characterizes this kind of accidents. ![]() ![]() In particular, the analysis and comparison between the transients initiated by an unmitigated double-ended cold leg rupture and an unmitigated double-ended hot leg rupture in the loop 1 of the primary cooling system is presented herein. The aim of this paper is to present the analysis of MELCOR code calculations concerning two independent unmitigated large break loss of coolant accident transients, occurring in the cited type of reactor. In the framework of severe accident research activity developed by ENEA, a MELCOR nodalization of a generic Pressurized Water Reactor of 900 MWe has been developed. Analysis of unmitigated large break loss of coolant accidents using MELCOR code
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