Uncertainty Quantification in (α,n) Neutron Source Calculations for an Oxide Matrix Journal April, 2016
An Assessment of Coupling Algorithms for Nuclear Reactor Core Physics Simulations ... Journal April, 2016
Capabilities, Implementation, and Benchmarking of Shift, a Massively Parallel Monte Carlo Radiation Transport Code... Journal March, 2016
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
A Method for Including External Feed in Depletion Calculations with CRAM and Implementation into ORIGEN... Journal November, 2015
