Fiscal Year 2016 Report on SCALE Maintenance and Development (ORNL/SR-2017/152) Technical Report January, 2017
Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor (ORNL/TM-2016/742) Technical Report January, 2017
Guide to Performing Computational Analysis of Criticality Accident Alarm Systems ORNL/TM-2013-211 Technical Report January, 2017
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
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