Design of a separate effects MiniFuel irradiation experiment investigating microstructure evolution in high burnup UO2 Journal May, 2025
Swelling and Fission Gas Release of U-10Mo and U-17Mo Following Neutron Irradiation at 250 – 500°C Journal April, 2025
Californium-252 production at the High Flux Isotope Reactor − I: Validation study using campaign data Journal February, 2025
Status of GPU capabilities within the Shift Monte Carlo radiation transport code Conference Paper January, 2025
Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems... Conference Paper November, 2012
Data Adjustment Exercises for Fast Reactor Benchmark Problems Using SCALE... Conference Paper November, 2012
A New Semi-Implicit Direct Kinetics Method with Analytical Representation of Delayed Neutrons... Conference Paper November, 2012
Comparison of Hybrid Methods for Global Variance Reduction in Shielding Calculations Conference Paper November, 2012
