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.

Keywords

• criticality, metallic core, MOX core, FCA, MCNP-4C, ENDF/B-VI