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AbstractAbstract
[en] Accident transient due to the loss of flow in the Process Inherent Ultimate Safety (PIUS) reactor has been simulated. This simulation constitutes a part of the safety analysis in the advanced nuclear reactor design which is inherently safe such as PIUS reactor having the thermal power of 2000 M Wth (PIUS2000). The analysis was 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 was done in Nagoya University of Japan by 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) occurred due to the failure of the primary pump
Original Title
SIMULASI TRANSIEN KEHILANGAN ALIRAN PENDINGIN DALAM REAKTOR PIUS MENGGUNAKAN RELAP5/MOD2
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Source
Sudjatmoko; Karmanto, Eko Edy; Supartini, Endang (Yogyakarta Nuclear Research Center, National Nuclear Energy Agency, Yogyakarta (Indonesia)); Yogyakarta Nuclear Research Center, National Nuclear Energy Agency, Yogyakarta (Indonesia); 285 p; ISSN 0216-3128; ; Apr 1996; p. 144-150; Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology; Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan Teknologi Nuklir; Yogyakarta (Indonesia); 23-25 Apr 1996; Available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 5 refs.; tabs.; 14 figs.
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