Axial Moderator Density Distributions, Control Blade Usage, and Axial Burnup Distributions for Extended BWR Burnup Credit (NUREG/CR-7224, ORNL/TM-2015/544) January, 2016
U. S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968 -2013 (NUREG/CR-7227) 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) 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) 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) January, 2016
Neutron Activation and Thermoluminescent Detector Responses to a Bare Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2015/462) January, 2016
Development of a SCALE Model for High Flux Isotope Reactor Cycle 400 (ORNL/TM-2011-367) 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) January, 2012