Publications Details
AP600 design basis and severe accident scoping calculations with the CONTAIN code
The Westinghouse AP600 plant is one of a number of new reactor plant concepts being proposed by industry. One of the unique design features of the AP600 plant is the method by which the containment is cooled during a reactor accident. Through the passive containment cooling system (PCCS), the containment steel shell is passively cooled by natural convection of air and by water film evaporation from the shell exterior surface. In this study an analysis of the AP600 plant was conducted for postulated design basis accident (DBA) and severe accident scenarios using the NRC containment code CONTAIN2 with new code enhancements to model water film transport and evaporation on the exterior of the containment shell.