Nuclear Data Uncertainty Analysis to Meet the Target Accuracy Requirements on the MYRRHA k(eff)

MYRRHA is a flexible experimental facility being designed at the SCK CEN, in Mol, Belgium. Cooled by lead-bismuth, it is conceived to operate both in sub-critical mode, as an accelerator driven system, and in critical mode, as a fast reactor. In order to comply with MYRRHA reactor design requirements, uncertainties due to nuclear data must be quantified. Significant gaps between the uncertainties and the target accuracies have been systematically shown in the past. In this paper, first, a Sensitivity and Uncertainty analysis with JEFF -3.3 nuclear data library of the effective neutron multiplication factor k(eff) of the latest MYRRHA reactor design - v1.8 - is presented. Then, since target accuracy for k(eff) of 300 pcm is exceeded, a Target Accuracy Requirement assessment is performed in order to find out the required accuracy on cross section data to meet the requested target accuracy. To reach the requested target accuracy, a reduction of the uncertainty in the fission and capture cross sections of Pu-240 JEFF -3.3 evaluation is needed.