PENGARUH KEHILANGAN ALIRAN PENDINGIN SEKUNDER TERHADAP PARAMETER TERMOHIDROLIK TERAS REAKTOR TRIGA 2000 BANDUNG

PENGARUH KEHILANGAN ALIRAN PENDINGIN SEKUNDER TERHADAP PARAMETER TERMOHIDROLIK TERAS REAKTOR TRIGA 2000 BANDUNG. Untuk mendapatkan informasi lengkap tentang kondisi kegagalan sistem pendingin sekunder, telah dilakukan simulasi kejadian kehilangan aliran pendingin sekunder reaktor TRIGA 2000 Bandung ketika beroperasi pada daya 2000 kW, menggunakan program komputer RELAP5/MOD3.2. Pada penelitian ini teras reaktor TRIGA 2000 Bandung dimodelkan dalam bentuk teras tujuh kanal. Dalam simulasi ini diasumsikan bahwa motor penggerak pompa sekunder kehilangan catu daya, sehingga gagal berfungsi. Hasil perhitungan dalam kondisi tunak diperoleh awal kondisi tunak tercapai setelah 2500 detik dari sejak reaktor mulai beroperasi pada daya 2000 kW, suhu kelongsong kanal terpanas adalah 150,63°C, suhu pendingin keluar kanal terpanas adalah 111,36°C, suhu masuk reaktor 35,52°C, dan suhu keluar reaktor 45,75°C. Hasil perhitungan transien memperlihatkan, sebelum terjadi scram suhu kelongsong kanal terpanas 159,78°C dan suhu pendingin keluar kanal terpanas 115,86°C. Setelah terjadi scram yaitu 150 detik setelah kegagalan pompa sekunder suhu pendingin keluar dan suhu pendingin masuk reaktor terus mengalami kenaikan hingga mencapai 53,15°C yang berasal dari panas sisa peluruhan. ;

THE INFLUENCE OF LOSS OF SECONDARY COOLANT FLOW TO THERMOHYDRAULIC PARAMETER OF BANDUNG TRIGA 2000 REACTOR CORE. To get complete information about condition of failure of secondary cooling system, the simulation of loss of secondary coolant flow of Bandung TRIGA 2000 reactor under the operation of 2000 kW power has been done, by applying computer program RELAP5/MOD3.2. At this research, core of Bandung TRIGA 2000 reactor is modeled in the form of seven channels core. On this simulation was assumed that secondary pump actuator got loss of power, so failed in function. The result of calculation in condition of steady state indicated that the initial condition of steady state was reached 2500 seconds after reactor started operation on 2000 kW power, the hottest channel cladding temperature was 150,63°C, the hottest channel coolant outlet temperature was 111,36°C, reactor inlet temperature was 35,52°C, and reactor outlet temperature was 45,75°C. The result of calculation in transient condition showed that before scram occurred, the hottest channel cladding temperature was 159,78°C and the hottest channel coolant outlet temperature was 115,86°C. After scram occurred, that was 150 seconds after failure of secondary pump, reactor inlet and reactor outlet temperature were always increasing to 53,15°C due to the heat of fission product.