Fuel Cycle Assessment: Evaluation and Analyses using ORION for US Fuel Cycle Options... Conference Paper November, 2014
Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors Conference Paper November, 2014
Fully Ceramic Microencapsulated (FCM) Fuel in FHRs: A Preliminary Reactor Physics Assessment... Conference Paper November, 2014
Optimization and Parallelization of the Thermal-Hydraulic Sub-channel Code CTF for High-Fidelity Multi-physics Applications... Journal November, 2014
Mixed Uranium-Plutonium Solution Validation of KENO V.a and KENO-VI in SCALE 6.1.2 and 6.2b3 Using Multigroup and Continuous-Energy ENDF/B-VII.0 Libraries Conference Paper November, 2014
Coupled Neutronics Thermal-Hydraulic Solution of a Full-Core PWR Using VERA-CS... Conference Paper September, 2014
An Inventory Analysis of Thermal-spectrum Thorium-fueled Molten Salt Reactor Concepts: Supporting U.S. Fuel Cycle Assessment Conference Paper September, 2014
Design, Fabrication, and Modeling of a Two-Phase Thermosyphon Experimental Facility for Fuels and Materials Irradiation... Conference Paper September, 2014
