Fission Product Release Characteristics into Containment under Design Basis and Severe Accident Conditions,

摘要

A detailed review of the radiological release estimates for light water reactor accident sequences is presented as a basis for development of a simplified approach for prediction of characteristics of radiological releases into containments under design basis and severe accident conditions for both Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). Resulting source term estimates are also compared with parallel results using the Source Term Code Package (STCP) methodology.