Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
LOSS OF FLOW TRANSIENT SIMULATION IN PIUS REACTOR USING RELAP5/MOD2. Accident transient due to the loss of flow in the Process Inherent Ultimate Safety (PIUS) reactor have been simulated. This simulation constitute a part of the safety analysis in the advanced nuclear reactor design which inherently safe such as PIUS reactor having the thermal power of 2000 MWth (PIUS 2000). The attention of analysis has been focused on the accidental transient of loss of flow due to the loss of power supply to the primary pumps that can result from a loss of off site power. Simulation has been done in Nagoya University of Japan using computer code RELAP5/MOD2. The effect of heat structures on the coolant flow rate through the core during the phase of natural circulation through density lock and borated water pool has been analyzed. The simulation results showed that the cyclic behavior of natural circulation through the pool, density lock and riser (core) will be occurred due to the trip of the primary pump.
Keywords : PIUS type Reactor, Primary Pump Speed, Pressure Balance, Transient Simulation Test, Density Lock, RELAP5/MOD2.
Published : Proceeding "Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir", Yogyakarta, 23-25 April 1996, ISSN No. : 0216-3128
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