SCRAM-Discharge Volume Break Studies. Part 2. Fission-Product Transport Analyses

摘要

This portion of the ORNL-SASA presentation deals with the analysis of the rate of movement of fission products from the overheated core through a series of reactor control volumes, the final one being the exterior of the reactor building. At this time, the analysis of a complete station blackout sequence at Browns Ferry has been completed. The fission product transport portion of the study was presented in preliminary form at the 1981 Water Reactor Safety Meeting. Currently, the analysis of the small-break LOCA outside of the containment is in process. The initial study traced noble gases and iodine through the reactor systems during the event sequence; the current work includes an analysis of cesium transport in addition to noble gases and iodine. (ERA citation 08:005184)