Fiscal Year 2016 Report on SCALE Maintenance and Development (ORNL/SR-2017/152) Technical Report January, 2017
The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors Journal January, 2017
Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis Journal January, 2017
In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification Conference Proceeding January, 2017
High-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design Journal January, 2017
Heat Deposition Analysis for the the High Flux Isotope Reactor's HEU and LEU Core Models Journal January, 2017
Role of the Radiation Safety Information Computational Center (RSICC) in Knowledge Management Conference Proceeding January, 2017
International Secure Platform for Export-Controlled Computing Tools Conference Proceeding January, 2017
A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT Journal January, 2017
