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[en] The thermalhydraulic analysis of the mini fuel element that will be irradiated in RSG-GAS, was done. The mini fuel element consists of mini fuel plates assembled in 7 segments with 4 different uranium loadings. The element will be placed in a stringer to be positioned at irradiation position D-9. The thermalhydraulic safety analysis was carried out by assuming that all mini fuel plates were loaded at the highest uranium loading (i.e. 5.20/gcm3). Mini fuel element will be irradiated along 7 cycles to get maximum bum up and strength material. The nuclear peaking factors and flow rates of the mini fuel element were assumed to be the same with the designed value stated in the SAR of RSG-GAS. The calculation was done by using the computer code COOLOD-N and the analysis was conducted at the worst condition
Source
Suripto, A.; Yuwono, I.; Nasution, H.; Hersubeno, B.J.; Amini, S.; Sigit; Cahyono, A. (Nuclear Fuel Elements Development Centre, National Atomic Energy Agency, Serpong, Indonesia (Indonesia)); Nuclear Fuel Elements Development Centre, National Atomic Energy Agency, Serpong, Indonesia (Indonesia); 389 p; ISSN 1410-1998; 
; Nov 1996; p. 266-273; Scientific Presentation on Nuclear Fuel Cycle; Presentasi Ilmiah Daur Bahan Bakar Nuklir; Jakarta, Indonesia (Indonesia); 18-19 Mar 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, Indonesia (ID); authors; 5 figs.; 1 tab.; 6 refs.
; Nov 1996; p. 266-273; Scientific Presentation on Nuclear Fuel Cycle; Presentasi Ilmiah Daur Bahan Bakar Nuklir; Jakarta, Indonesia (Indonesia); 18-19 Mar 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, Indonesia (ID); authors; 5 figs.; 1 tab.; 6 refs.