Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP Keff Calculations for PWR Burnup Credit Casks (NUREG/CR-7205, ORNL/TM-2012/544) Technical Report January, 2015
Bias Estimates Used in Lieu of Validation of Fission Products and Minor Actinides in MCNP Keff Calculations for PWR Burnup Credit Casks (NUREG/CR-7205, ORNL/TM-2012/544) Technical Report January, 2015
Development of a SCALE Model for High Flux Isotope Reactor Cycle 400 (ORNL/TM-2011-367) Technical Report January, 2012
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Criticality (keff) Predictions (NUREG/CR-7109, ORNL/TM-2011/514) Technical Report January, 2012
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions (NUREG/CR-7108, ORNL/TM-2011/509) Technical Report January, 2012
Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis (NUREG/CR-7107, ORNL/TM-2011/161) Technical Report January, 2012