Assessment of Fission Product Cross-Section Data for Burnup Credit Applications

Leal, L.C.; Derrien, H.; Dunn, Michael E.; Mueller, Don

doi:10.2172/932626

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Snf Fuel Characterization1

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2015

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“…Extensive investigations for PWR fuel have been performed domestically and internationally in an effort to evaluate and license the technical bases related to burnup credit (Radulescu et al 2012, Scaglione et al 2012, which include predictions of isotopic concentrations as a function of in-reactor irradiation parameters, evaluation of fission product and actinide cross sections for use in the depletion analysis (Leal et al 2007), and criticality modeling assignment of burnup values for discharged SNF based on reactor records and/or measurements as required by ISG-8.…”

Section: Snf Fuel Characterizationmentioning

confidence: 99%