Development of ORIGEN Libraries for Mixed Oxide (MOX) Fuel Assembly Designs... Journal February, 2016
Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Journal February, 2016
Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation Journal January, 2016
The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation... Journal December, 2015
Doppler Broadening by Linear Combination of Reference Temperature Cross Sections - L2 kernel-minimizing cross section temperature interpolation methods Conference Paper November, 2015
ORIGAMI: A New SCALE Interface for Fuel Assembly Characterization with ORIGEN... Conference Paper November, 2015
SAMINT: A New Evaluation Tool to Perform Resonance Parameter Data Adjustments based on Integral Experiment Data... Conference Paper November, 2015
A Proposed Spent Nuclear Fuel Storage and Transportation Licensing Approach Using As-loaded Analysis... Conference Paper November, 2015
Deterministic Fission Matrix Acceleration of Monte Carlo Calculations Conference Paper November, 2015
