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

abstract

  • 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.

author list (cited authors)

  • Hari, S., Tu, J., & Hassan, Y. A.

publication date

  • December 1998