Uncertainty Quantification with the Event-by-Event Fission Model FREYA

摘要

In the absence of high quality uncertainty information on nuclear data, uncertainty information generated by FREYA may be useful in providing quantitative uncertainty estimates in both experimental studies and in calculations performed by particle transport codes. On the experimental side, the generated covanance data can be used to propagate uncertainties in calculations and assays. In addition, source term neutron and gamma energy and multiplicity information can be generated by FREYA in particle transport simulations which produce full statistical distributions. Varying parameters around their best fit values can help understand systematic uncertainties in the output. The optimal minimization method is under study Once the method has been chosen, values of the best fit parameters and their associated uncertainties will be determined for (252)~Cf, as well as for the other nuclides available in FREYA.