Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit (NUREG/CR-7224, ORNL/TM-2015/544) Technical Report January, 2016
U.S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013 (NUREG/CR-7227) Technical Report January, 2016
U. S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968 -2013 (NUREG/CR-7227) Technical Report January, 2016
Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit (NUREG/CR-7224, ORNL/TM-2015/544) Technical Report January, 2016
Neutron Activation Foil and Thermoluminescent Dosimeter Responses to a Polyethylene Reflected Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2016/317) Technical Report January, 2016
Neutron Activation Foil and Thermoluminescent Dosimeter Responses to a Lead Reflected Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2016/316) Technical Report January, 2016
Neutron Activation and Thermoluminescent Detector Responses to a Bare Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2015/462) Technical Report January, 2016
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel Technical Report January, 2000
Review and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel (NUREG/CR-6665, ORNL/TM-1999/303) Technical Report January, 2000