Analysis of a research reactor under ATWS events using the RELAP5/MOD3.2 computer code

Thermal hydraulic simulations for two series of transients for a hypothetical research reactor moderated and cooled by heavy water circulating under atmospheric pressure were carried out using the RELAP5/MOD3.2 computer program. These simulations represent a step towards state-of-the-art analyses of hypothetical events in research reactors such as the HIFAR (High Flux Australian Reactor) reactor (Connoly and Clancy, 1993) in Australia. Simulations to date have focused on thermal-hydraulic predictions without incorporating reactivity feedback effects essential for a correct simulation of a reactor. The first series of transients simulated the combined failure of the primary coolant circulation pumps and the reactor protection system, and the second series of transients simulated the non-availability of heat exchangers without reactor scram. In both of the cases, the emergency core cooling system ECCS was simulated as being unavailable.

Proceedings of the 1998 Thirteenth Australasian Fluid Mechanics Conference, Melbourne, Australia, 13-18 December 1998 (Volume 2)

Analysis of a research reactor under ATWS events using the RELAP5/MOD3.2 computer code Conference Paper