<![CDATA[The calculation of fission reaction rate and capture reaction with and without filters have been done using the REACT of SRAC. The calculation of fission rate on fuel 1 and 2 were 5,39 x 10-2 reaction/cm3s with filter and 6,35 x 10-2 reaction/cm3s without filter, then of capture reaction rate with filter on fuel 1 and 2 were 2,91 x 10-2 reaction/cm3s, without filter on fuel 1 was 3,9 x 10-2reaction/cm3s and fuel 2 was 3,78 x 10-2 reaction/cm3s. The calculation of capture reaction on cladding with filter was higher than without filter was 2,15 x 10-3 reaction/cm3s, on moderator with filter was lower than without filter was 3,18 x 10-3 reaction/cm3s. The highest neutron spectrum with 1% enrichment of experiment 1 in thermal energy was 6,31 x 10-6 MeV-1 and in fast energy was 6,44 x 10-6 MeV-1, and decreased constantly. Meanwhile of experiment 2, neutron spectrum in thermal energy was 1,37 x 10-5 MeV-1 and in fast energy was 6,91 x 10-6 MeV-1, and decreased significantly from 1% to 2% enrichment then decreases constantly until 5% enrichment]]>
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