Impact of Meltdown-Accident Modeling Developments on PWR Analysis

摘要

Models recently incorporated into a new version of the MARCH computer code have altered earlier estimates of some parameter responses during meltdown accidents of PWRs. These models include improved fuel-coolant heat transfer models, new core radiative heat transfer models, improved in-vessel flashing models, improved models for burning of combustible gases in containment, and CORCON1 models for core-concrete interactions. Studies performed with these models have been used to identify and, in some cases, bound meltdown accident analysis uncertainties. (ERA citation 07:059607)