DIAGNOSIS OF THE UNRESOLVED DOMAIN TREATMENT IN MONTE CARLO TRANSPORT CALCULATIONS THROUGH THE IDENTIFICATION AND MODELLING OF CRITICALITY SAFETY EXPERIMENTS

Monte Carlo neutron transport codes can be used for high-fidelity predictions of the performance nuclear systems. However, validation against experiments is required in order to establish credibility results and identify inaccuracies due calculation scheme associated databases. The International Handbook Evaluated Criticality Safety Benchmark Experiments (ICSBEP) contains criticality safety benchmarks derived from that have been performed at various critical facilities around world are very valuable purposes. main objective this work identification modelling experimental included ICSBEP support calculations when applied fast systems, particular, KENO-VI AMPX-formatted continuous-energy libraries SCALE package. In such predicted k-eff values sensitive treatment data Unresolved Resonance Region (URR). Consequently, with intermediate spectra identified modelled KENO-VI. Then, calculated without probability tables URR compared each other most configurations URR. As a result proposed study, recommendations given about should analysed qualify processed before their use practical reactor applications.