The simultaneous determination of 235U and 239Pu using delayed neutron activation analysis Journal January, 2013
Performance assessment of self-interrogation neutron resonance densitometry for spent nuclear fuel assay Journal January, 2013
A neutronic investigation of the use of fully ceramic microencapsulated fuel for Pu/Np burning in PWRs Journal January, 2013
Neutronics and Depletion Methods for Parametric Studies of Fluoride Salt Cooled High Temperature Reactors with Slab Fuel Geometry and Multi-Batch Fuel Management Schemes Journal January, 2013
Verification of a Depletion Method in SCALE for the Advanced High Temperature Reactor Journal January, 2013
Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling Journal January, 2013
Determination and Application of Partial Biases in Criticality Safety Validation Journal January, 2013