MCNP modelling of the LMT-006 integral criticality benchmark experiment

Based on the data available from ICSBEP (International Handbook of Evaluated Criticality Safety Benchmark Experiments) handbook CAD (Computer Assisted Design) models of all thirty different configurations of the LMT-006 benchmark experiment were created. Based on these models MCNP (Monte Carlo N-Particle transport code) compatible input files were produced using the GRASP tool. The new MCNP models were validated against the results from existing models. The models were used to validate never nuclear data libraries such as JEFF-3.2 and ENDF/B-VII.1.