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On the Analysis and Evaluation of Direct Containement Heating with the Multidimensional Multiphase Flow Code MC3D



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Science and Technology of Nuclear Installations / Volume 2010 (2010)

Type de document > *Article de revue

Mots clés >

Unité de recherche > IRSN/DSR/SAGR/BPhAG

Auteurs > MEIGNEN Renaud, JANIN Tanguy

Date de publication > 01/01/2010


In the course of a postulated severe accident in an NPP, Direct Containment Heating (DCH) may occur after an eventual failure of the vessel. DCH is related to dynamical, thermal, and chemical phenomena involved by the eventual fine fragmentation and dispersal of the corium melt out of the vessel pit. It may threaten the integrity of the containment by pressurization of its atmosphere. Several simplified modellings have been proposed in the past but they require a very strong fitting which renders any extrapolation regarding geometry, material, and scales rather doubtful. With the development of multidimensional multiphase flow computer codes, it is now possible to investigate the phenomenon numerically with more details. We present an analysis of the potential of the MC3D code to support the analysis of this phenomenon, restricting our discussion to the dynamical processes. The analysis is applied to the case of French 1300 MWe PWR reactors for which we derive a correlation for the corium dispersal rate for application in a Probabilistic Safety Analysis (PSA) level 2 study.

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Laboratoire IRSN impliqué

 Bureau de physique des accidents graves (BPhAG)