An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses--Criticality (keff) Predictions Journal December, 2014
Neutronics Studies of Uranium-bearing Fully Ceramic Micro-encapsulated Fuel for PWRs Journal December, 2014
Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors Conference Paper November, 2014
Preliminary Design of Laser - induced Breakd own Spectroscopy for Proto - MPEX... Conference Paper November, 2014
Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses... Journal November, 2014
Detection and analysis of particles with failed SiC in AGR-1 fuel compacts... Conference Paper October, 2014
Performance of AGR-1 High-Temperature Reactor Fuel During Post-Irradiation Heating Tests... Conference Paper October, 2014
Modeling of irradiation Hardening of Iron after Low Dose and Low Temperature Neutron Irradiation... Journal September, 2014
Fully Ceramic Microencapsulated Fuels: Characteristics and Potential LWR Applications Conference Paper September, 2014
