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DOI: 10.1615/ICHMT.1995.RadTransfProcHeatMassTransfSevNuclReactAcc.320

A. G. Popkov
IBRAE/RAS, Moscow, Russia

V. V. Chudanov
IBRAE/RAS, Moscow, Russia

V. F. Strizhov
Nuclear Safety Institute, Russian Academy of Sciences, Bolshaya Tul'skaya 52, Moscow 113191, Russia

P. N. Vabishchevich
Institute for Mathematical Modelling, RAS, Moscow, Russia

J. C. Latche
Institut de Protection et de Sûrete Nucléaire, Département de Recherches en Sécurité, Service d'Etudes et de Modelisation d'Accidents de Reacteurs -CE Cadarache - 13108 St Paul-Lez-Durance CEDEX - France

J. M. Veteau
CEA/DRN/DTP/STR, Grenoble, France


Severe accidents are presently studied worldwide and, in particular, research programs concerning corium spreading after vessel failure are carried out at the same time in IBRAE (Russia), in IPSN and in CEA/DRN (France). This paper deals with the validation of the Russian spreading code RASPLAV/SPREAD against some results of an experimental program performed in France, namely CORINE.
The RASPLAV/SPREAD code is developed in IBRAE/RAS for numerical modeling of melt spreading phenomena. The code includes two and three dimensional solvers for prediction of corium flow and calculation of heat transfer in the corium, basemat and metallic constructions. It copes with phase transition phenomena, corium internal heat generation and different types of cooling conditions.
The CORINE program investigates the behavior during spreading of various simulant materials: the first two series of tests have already been performed, using water-glycerol mixtures, tests of low melting-point alloys are underway. In this paper we will assess the code against two CORINE tests, corresponding to spreading of pure glycerol under different flow rate conditions. The numerical models of flow which has been used is base on the approximation of a thin layer.

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