Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation Journal January, 2016
U. S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968 -2013 (NUREG/CR-7227) Technical Report January, 2016
Uncertainty quantification in (α,n) neutron source calculations for an oxide matrix Journal 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