In the frame of WP4 of SARNET Project regarding ASTEC benchmarks on reactor applications, the V1.1 version of ASTEC code has been assessed on TMI-2 accident to evaluate the capability of the code to simulate severe accident in nuclear power plant. The present analysis has been limited to the first two phases of the accident just prior to core reflood. A sensitivity analysis to most important and uncertain core degradation parameters has been carried out to investigate their influence on hydrogen generation and core melting. Finally, the ASTEC results have been compared with the results of new applications of ICARE/CATHARE and SCDAP/RELAP5 codes.

TMI-2 Accident Analysis with ASTEC V1.1 Code and Comparison with ICARE/CATHARE and SCDAP/RELAP5

Bandini, G.
2005-06-23

Abstract

In the frame of WP4 of SARNET Project regarding ASTEC benchmarks on reactor applications, the V1.1 version of ASTEC code has been assessed on TMI-2 accident to evaluate the capability of the code to simulate severe accident in nuclear power plant. The present analysis has been limited to the first two phases of the accident just prior to core reflood. A sensitivity analysis to most important and uncertain core degradation parameters has been carried out to investigate their influence on hydrogen generation and core melting. Finally, the ASTEC results have been compared with the results of new applications of ICARE/CATHARE and SCDAP/RELAP5 codes.
Rapporto tecnico;Reattori nucleari ad acqua;Sicurezza nucleare;Analisi incidentale
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5209
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