Community Research and Development Information Service - CORDIS


Extended studies on the safety of Light Water Reactors (LWRs) have emphasized the important role of ex-vessel melt behaviour during postulated severe core meltdown accidents. Large scale experiments with prototypical materials, as well as theoretical models on the important processes during molten core concrete interaction (MCCI) have been a subject of intense research for more than a decade. The aim of this report is to summarise the state-of-the-art in the most important areas and to identify those topics which are sufficiently known and which topics need additional evaluation. Pressurized water reactor (PWR) and boiling water reactor (BWR) accident scenarios are analyzed. The influence of water during the erosion process and its possible consequences on melt coolability and fission product release is discussed. The report also discusses the development of future LWRs with the possibility of engineered ex-vessel corium coolability and corium retention devices. Areas of research where additional generic investigations are required to enable a conceptual design and verification of ex-vessel core retention concepts are summarized.

Additional information

Authors: PAROZZI F, ENEL/ATN/GNUM (IT);VIDARD M, EDF/EPTN, Villeurbanne (FR);FIORAVANTI D, Politecnicodi Milano, DNE (IT);LOCATELLI S, Politecnicodi Milano, DNE (IT);ALSMEYER H, Forschungszentrum Karlsruhe GmbH (DE);FOIT J J, Forschungszentrum Karlsruhe GmbH (DE);HOWE L D, AEA Fusion, Culham Laboratory,Abingdon (GB);TURLAND B D, AEA Technology, Winfrith Laboratory (GB);CENERINO G, IPSN/DPEI/SEAC (FR);CORDFUNKE E H P, Energieonderzoek Centrum Nederland (NL);HUNTERLAAR M E, Energieonderzoek Centrum Nederland (NL);FISCHER M, Siemens/KWU, Erlangen (DE);WEGENER D, Siemens/KWU, Erlangen (DE);SZABO I, CEA/DRN/DER/SIS (FR)
Bibliographic Reference: EUR 16649 EN (1995) 422pp., FS
Availability: Available from the European Commission, Mr G Cottone, DG XII-F-5, 200 rue de la Loi, B-1049 Bruxelles (BE)
ISBN: ISBN 92-827-5228-3
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