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[en] Cooling system is important component in RSG-GAS. To carry out the transient simulation of one line-cooling mode, the model of RSG-GAS has been prepared. To illustrate the transient condition, the RELAP5.MOD3 computer code the existing input files were used. This Input consist of kinetic, thermal, hydraulic and geometries data. Modification and decrement of number of nodalization has been done to simplification as well as running time. The reasonable result of model is arranged to determine the initial condition of input data therefore steady state condition have agreement to the analysis result of one line cooling mode of RSG-GAS. Parameter investigated are transient temperatures of cooling system after decreasing of secondary cooling system occur as function of time. These parameters can be requested using input of Minor Edit Request Simulation is conducted at the reactor power of 15 MW steady-state for one-line cooling mode in which the primary and secondary cooling of 430 kg/sec and 550 kg/sec respectively. Decreasing of secondary cooling flow is caused by pump trip. As a consequence, the control rod drop due to reactor protection system. The negative reactivity of control rod causes decreasing of reactor power. Change of pattern for the primary and secondary cooling system can be known. After that simulation depicts that increasing of temperatures occur at the certain moment since initiation temperature conditions, due to reactor shut down, curve inclined move going down. (author)
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Endiah Puji Hastuti; Setiyanto; Taswanda Taryo; Mohammad Dhandhang Purwadi; Pinem, Surian; Tarigan, Alim; Hasibuan, Djaruddin; Kadarusmanto; Amir Hamzah (Centre for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Centre for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia); 288 p; ISSN 0854-5278; 
; May 2004; p. 95-104; Seminar on Research Result of Research Reactor Technology Centre 2003; Seminar Hasil Penelitian P2TRR Tahun 2003; Serpong (Indonesia); 24-25 Feb 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 6 refs.; 1 tab.; 7 figs.
; May 2004; p. 95-104; Seminar on Research Result of Research Reactor Technology Centre 2003; Seminar Hasil Penelitian P2TRR Tahun 2003; Serpong (Indonesia); 24-25 Feb 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 6 refs.; 1 tab.; 7 figs.