KAMINI reactor benchmark analysis

Monte Carlo modeling of the Kalpakkam Mini reactor (KAMINI) had been made earlier by us for the first time using Monte Carlo code (MCNP4A) and ENDF/B-VI.2 data in the year 2004. KAMINI has been accepted as a part of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) recently and its detailed configuration is available for analysis in the International Handbook of Evaluated Criticality Safety Benchmark Experiments, 2006. New neutron cross section data is also now available for nuclides of thorium–uranium fuel cycle through IAEA coordinated research and these are based on ENDF/B-VII. Examination of the new cross section data for nuclides 233U and 27Al, the major constituents in the fuel alloy of KAMINI, shows the addition of more resolved resonance structure in them. Hence, a review of our earlier work is made using new cross section data and by using the improved MCNP model of KAMINI supplied by ICSBEP evaluators. It is observed that by using the new data keff value changed from 0.9890 to 0.99357 and is closer to the experimental value.