Comparison of the SCDAP computer code with bundle data under severe accident conditions

The SCDAP computer code, which is being developed under the sponsorship of the United States Nuclear Regulatory Commission, models the progression of light water reactor core damage including core heatup, core disruption and debris formation, debris heatup, and debris melting. SCDAP is being used to help identify and understand the phenomena that control core behavior, during a severe accident, to help quantify uncertainties in risk assessment analysis, and to support planning and interpretation of severe fuel damage experiments and data. The first version of the code, SCDAP/MODO, has undergone extensive assessment over the past year. Comparisons between SCDAP calculations and data from the Severe Fuel Damage (SFD) Test Series being performed at the Idaho National Engineering Laboratory and the Hagen meltdown experiments being performed in Karlsruhe, West Germany, were essential parts of that assessment. Comparisons for two experiments, SFD Scoping Test (ST) and ESSI-2, are presented in this paper. (orig./RW)