Introduction of uncertainty evaluation in reactor core design study; Application for FR and ADS

Kugo, Teruhiko 

Basic Ideas are introduced to evaluate the uncertainty in neutronic characteristics. The theoretical method how to evaluate uncertainty due to cross section errors will be shown by using sensitivity coefficient and covariance data. Sensitivity analysis based on generalized perturbation theory is introduced. As practical cases, uncertainty evaluation results are shown for a MA-loaded fast reactor core and an accelerator driven system. Uncertainty evaluation methods, cross section adjustment method, conventional bias factor method, extended bias factor methods to improve prediction accuracy with use of integral experimental data are introduced. Uncertainty evaluation results with use of the above methods are shown together with discussion of impact of expected integral experiments using MA-bearing fuel on the prediction accuracy improvement.