Accident progression and radiological analyses of the interfacing system loss of coolant accident for a typical pressurized water reactor

This paper is intended to evaluate of the characteristics of a fission product source termrelease or distribution during ISLOCA with the modeling of an auxiliary building in a typical 1000MWPWR. The focuses of the analyses are for (1) the fission product release from the reactor core, (2) the fission product distributions in a reactor coolant system, a molten corium, reactor vessel, or auxiliary building, (3) the fission product release from the auxiliary building, and (4) the scrubbing effect through the water pool that can reduce the amount of soluble fission products. The paper describes a brief methodology, accident progression analysis, and the fission product distributions. The characteristics of a fission product source term with a modeling of auxiliary building are also discussed. Thermal hydraulic, severe accident phenomenological, or radiological analyses for an evaluation were conducted using the PWR version of MAAP5.