Methodology for an efficient statistical cross sections sampling in the unresolved resonance range

Cross sections are crucial nuclear data that describe the probability for a particular reaction to occur between an incident particle and target nuclide. In context of neutron transport, accurate cross section calculations notably in they provide input reactor physics criticality safety calculations. computed from large variety models sometimes involve experimental data, detail resonant shape at low energy. this paper, statistical contributions compound nucleus resonances investigated. This is particularly useful when artificial sets must be sampled, eg. framework ladder method used compute tables unresolved resonance range, where experimentally indistinguishable. The Monte Carlo based technique which (called ladders) sampled around reference energies range average parameters. methodology proposed estimate weight range. provides practical insights determine minimal number needed histories. methods present article can extended any physical problem on sampling resonances. particular, conclusions directly applied processing codes, some evaluation techniques require sampling, transport codes handle on-the-fly.