Two-Dimensional Neutronic and Fuel Cycle Analysis of the Transatomic Power Molten Salt Reactor (ORNL/TM-2016/742) Technical Report January, 2017
In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification Conference Proceeding January, 2017
Evaluation of the Concrete Shield Compositions from the 2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc SILENE Facility Conference Proceeding January, 2017
Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries Conference Proceeding January, 2017
2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc SILENE Facility Conference Proceeding January, 2017
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-Calvert Cliffs, Takahama, and Three Mile Island Reactors (NUREG/CR-6968, ORNL/TM-2008/071) Technical Report January, 2010
Analysis of Experimental Data for High Burnup PWR Spent Fuel Isotopic Validation-ARIANE and REBUS Programs (UO2 Fuel) (NUREG/CR-6969, ORNL/TM-2008/072) Technical Report January, 2010
Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel (NUREG/CR-6972, ORNL/TM-2008/015) Technical Report January, 2010
Technical Basis for a Proposed Expansion of Regulatory Guide 3.54-Decay Heat Generation in an Independent Spent Fuel Storage Installation (NUREG/CR-6999, ORNL/TM-2007/231) Technical Report January, 2010