Whole Core Analysis of an Open Pool Research Reactor under the Most Severe Loss of Coolant Accident Conditions

摘要

In the present work the accident in which either the outlet or the inlet coolant pipe connected to the bottom of the reactor tank in an open pool research reactor is completely ruptured, has been analyzed. The 3-D transient computer code ThEAP-I, developed in NRC ''Democritos'' has been utilized and applied to the 5 MW Greek Research Reactor (GRR-1). The results show that for GRR-1 a partial melting of the reactor core is possible. The amount of melting is roughly and conservatively estimated to be of the order of 20%. (ERA citation 12:008201)