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
Development of a SCALE Model for High Flux Isotope Reactor Cycle 400 (ORNL/TM-2011-367) Technical Report 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) Technical Report January, 2012
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses-Isotopic Composition Predictions (NUREG/CR-7108, ORNL/TM-2011/509) Technical Report January, 2012
Validation of SCALE for High Temperature Gas-Cooled Reactor Analysis (NUREG/CR-7107, ORNL/TM-2011/161) Technical Report January, 2012