[en] A research program aimed at the modelling of the corium ex-vessel behaviour is in progress in IPSN (Institut de Protection et de Surete Nucleaire) since 1994, to assess the safety of future PWRs core catchers. The resulting code, named CROCO, is briefly presented here under its first version mainly devoted to the spreading phase. The numerical procedure has been verified on academic problems (namely dam break problems) exhibiting analytical solutions. Moreover, validation tests have been successfully performed against CORINE experiments using glycerol and non-eutectic Bismuth-Tin alloy simulant, KATS tests using high temperature simulants and the first real material VULCANO test. Both verification and validation tests show a satisfactory agreement between CROCO V1.0 computations and reference results. (orig.)
Source
Alsmeyer, H. (ed.); Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Kern- und Energietechnik; Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung; 593 p; ISSN 0947-8620; 
; May 2000; p. 235-245; OECD Workshop on ex-vessel debris coolability; Karlsruhe (Germany); 15-18 Nov 1999; Available from TIB Hannover: ZA 5141(6475); 7 refs.
; May 2000; p. 235-245; OECD Workshop on ex-vessel debris coolability; Karlsruhe (Germany); 15-18 Nov 1999; Available from TIB Hannover: ZA 5141(6475); 7 refs.