The new concepts of Sodium-cooled Fast Reactors have to reach the Generation IV safety objectives. In this regard the Sodium Void Effect has to be minimized for the future projects of large-size SFR as well as the uncertainties on it. The Inst. of Radiological Protection and Nuclear Safety (IRSN) as technological support of French public authorities is in charge of safety assessment of operating and under construction reactors, as well as future projects. In order to state about the safety of new SFR designs the IRSN must be able to evaluate core parameters and their uncertainties. In this frame a sensitivity and uncertainty study has been performed to evaluate the impact of nuclear data uncertainty on sodium void effect, for the benchmark model of large SFR BN-800. The benchmark parameters (effective multiplication factor and sodium void effect) have been evaluated using two codes, the deterministic code ERANOS and the Monte Carlo code SCALE, while the S/U analysis has been performed only with SCALE. The results of the these studies point out the most relevant cross section uncertainties that affect the SVE and how efforts should be done in increasing the existing nuclear data accuracies. (authors)
[1]
Mark L Williams,et al.
Sensitivity and Uncertainty Analysis for Eigenvalue-Difference Responses
,
2007
.
[2]
Gerardo Aliberti,et al.
Methods in Use for Sensitivity Analysis, Uncertainty Evaluation, and Target Accuracy Assessment
,
2007
.
[3]
M. Salvatores,et al.
A Global Approach to the Physics Validation of Simulation Codes for Future Nuclear Systems
,
2008
.
[4]
Mihai Anitescu,et al.
Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems
,
2006
.