HAZARDS ANALYSIS EFFECTS OF STEAM GENERATOR TUBE RUPTURE Revision 1 Experiment GAS COOLED REACTOR

摘要

The purpose of the study is to review the basis for sizing the reactor coolant system relief valves and to determine possible effects of steam-graphite reaction in the event of a tube failure in the EGCR steam generator. In addition, the hazards aspects of steam generator water side depressurization rates are evaluated.