Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis Journal January, 2017
Molten Salt Reactor Neutronics and Fuel Cycle Modeling and Simulation with SCALE Journal January, 2017
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
Performance assessment of self-interrogation neutron resonance densitometry for spent nuclear fuel assay Journal January, 2013
A neutronic investigation of the use of fully ceramic microencapsulated fuel for Pu/Np burning in PWRs Journal January, 2013