Studi Perhitungan Benchmark Kritikalitas Teras Metalik dan MOX di FCA

Abstract

The criticality experiments at FCA three cores have been done to obtain
reliable original data as a benchmark test. The first two cores was mock-up of metallic
fueled LMFBR’s and the other was a mock-up of a MOX fueled LMFBR. The criticality
calculation of FCA cores was performed by using the Monte Carlo transport code
MCNP-4C in 2-D R-Z reactor geometry. The analysis was done with ENDF/B-VI
continuous energy neutron cross-section library at room temperature. The MCNP-4C
criticality prediction (keff) for metallic (XVI-1 and XVI-2) cores were underestimated in
0.54% and 0.48%, respectively. The MCNP-4C criticality prediction (keff) for MOX
(XVII-1) core showed best agreement with the experimental data where C/E value was
0.99995. In general, it can be concluded that MCNP-4C calculations on FCA criticality
benchmark experiments show a high accuracy for metallic as well as MOX cores.