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[en] To operate 3.55 g U/cc fueled RSG-GAS reactor, some neutronic characteristics such as reactivity value, burn-up characteristic, power factor distribution, and neutron flux distribution, must be known. The neutronic characteristic can be known by calculation with SRAC. The SRAC have 5 modules calculation that are PIJ, ANISN, TWOTRAN, TUD, CITATION and 2 options code that are ASMBURN, COREBN. In this research, reactivity value, burn-up characteristic, power factor distribution, flux neutron distribution were calculated with SRAC-ASMBURN for equilibrium 3.55 gr U/cc silicide RSG-GAS core. Cell burn-up calculation for preparation of fuel element and control rod element macroscopic cross section done with SRAC-PIJ module. The results of the ASMBURN were compared with the BATAN-2Diff results. Calculation result with ASMBURN shown that value of reactivity is 8.9% dk/k or 0,5% bigger then calculation result with BATAN-2Diff. Rate of fuel burn-up at EOC and power factor distribution at BOC smaller then result calculation using BATAN-2Diff, that are 0.45 % 235U (1.42%) and 0.01 (1.53%), respectively. The calculation result of flux thermal rate with ASMBURN is 1.0406 x E+14/(cm2.sec) with highest value is 1.389 x E+14/(cm2. sec) in E-5 position and lowest value is 0.7535 x E+14/(cm2.sec) in A-9 position. (author)
Source
Sukarsono, R.; Ganang Suradjijo (National Nuclear Energy Agency, Yogyakarta (Indonesia)) (eds.); Centre for Research and Development of Advanced Technology, National Nuclear Energy Agency, Yogyakarta (Indonesia); 265 p; ISSN 0216-3128; 
; 2002; p. 193-198; Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology; Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir; Yogyakarta (Indonesia); 27 Jun 2002; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 6 figs.
; 2002; p. 193-198; Scientific Meeting and Presentation on Basic Research in Nuclear Science and Technology; Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir; Yogyakarta (Indonesia); 27 Jun 2002; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 6 figs.