LOSS OF FLOW TRANSIENT SIMULATION IN PIUS REACTOR USING RELAP5/MOD2

LOSS OF FLOW TRANSIENT SIMULATION IN PIUS REACTOR USING RELAP5/MOD2
Ign. Djoko Irianto
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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FEEDBACK CONTROL SYSTEM ANALYSIS FOR PIUS TYPE REACTOR USING RELAP5/MOD2

FEEDBACK CONTROL SYSTEM ANALYSIS FOR PIUS TYPE REACTOR USING RELAP5/MOD2
Ign. Djoko Irianto
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
FEEDBACK CONTROL SYSTEM ANALYSIS FOR PIUS TYPE REACTOR USING RELAP5/MOD2. A reactor concept such as Process Inherent Ultimate Safety (PIUS) is a modification of Pressurized Water Reactor (PWR) in which the primary coolant system is submerged in a pool of poison water. Operating principle of this reactor is to maintain the pressure balance along the density lock which be a connection between the primary coolant system and the pool, so that no inflow through density lock. The pressure balance could be maintaned by controlling the primary pump speed using feedback control system. This feedback control system was simulated by experimental using thermal hydraulic test loop and by numerical simulation using RELAP5/MOD2. Numerical simulation is done by setting the thermal hydraulic test loop nodalization based on RELAP5/MOD2 norm input. The system nodalization is composed of 119 volumes, 127 junctions, and 106 heat structures. Analysis is carried out based on the result of experimental and numerical simulation. The two simulations gave some particularly parameters such as the primary pump speed, the primary flow rate, the poison water flow rate, and the primary coolant temperatures. Conclusion from the two simulation results, that is, feedback control system to the primary pump speed could be introduced to the operation of the PIUS reactor.

Keywords : Feedback Control System, PIUS type Reactor, Primary Pump Speed, RELAP5/MOD2, Pressure Balance, Numerical Simulation, Density Lock.
Published : Proceeding "Seminar Sains dan Teknologi Nuklir, Peningkatan Keselamatan Reaktor Triga Mark II Bandung", Bandung, 19-20 Maret 1997, ISSN No. : 1410-1769

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LOSS OF SECONDARY COOLANT ACCIDENT ANALYSIS FOR PIUS TYPE REACTOR USING RELAP5/MOD2

LOSS OF SECONDARY COOLANT ACCIDENT ANALYSIS FOR PIUS TYPE REACTOR USING RELAP5/MOD2

Ign. Djoko Irianto
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id

ABSTRACT
LOSS OF SECONDARY COOLANT ACCIDENT ANALYSIS FOR PIUS TYPE REACTOR USING RELAP5/MOD2. Process Inherent Ultimate Safety (PIUS) reactor concept is a reactor concept that intrinsically based on passive safety. This reactor refer to Pressurized Water Reactor (PWR) wherein the primary system is submerged in a pool of poison water. The operating principle is to maintain the pressure balance, so that no inflow from pool to the primary system. On loss of secondary coolant accident, primary coolant temperature increases, it is followed by the increase of primary pump speed. When the upper limit is reached, the pump is tripped. Due to the pressure balance disturbance, poison water flows from pool to the primary system, then reactor shut down. This accident condition was simulated by experimental and numerical simulation using RELAP5/MOD2. Numerical simulation was done to the experimental apparatus nodalization that was set on the norm of RELAP5/MOD2. This nodalization consist of 119 volumes, 127 junctions, and 106 heat structures. Analysis was carried out using both experimental and numerical simulation results. It can be concluded that PIUS type reactor is able to anticipate loss of coolant accident because its capability of self shut down.

Keywords : LOCA, PIUS type Reactor, RELAP5/MOD2, PWR.
Published : Proceeding of "Komputasi Dalam Sains dan Teknologi Nuklir VI", Jakarta, 16-17 Januari 1997.

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