Slides - Institiute of Nuclear Materials Management Annual Meeting (INMM), Atlanta GA, July 20-24, 2014
Slides - Institute of Nuclear Materials Management Annual Meeting, Atlanta GA, July 20-24, 2014
Slides - Institute of Nuclear Materials Management Annual Meeting (INMM), July 20-24 2014, Atlanta GA
This report describes a novel approach developed at the Oak Ridge National Laboratory
(ORNL) for the estimation of the uncertainty in the prediction of the neutron multiplication factor
for spent nuclear fuel. This technique focuses on burnup credit, where credit is taken in criticality
safety analysis for the reduced reactivity of fuel irradiated in and discharged from a reactor.
Validation methods for burnup credit have attempted to separate the uncertainty associated with
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
Slides - Institute of Nuclear Materials Management, 55th Annual Meeting, July 20 – 24, 2014 Atlanta, Georgia
