Fuel Assembly Reference Information for SNF Radiation Source Term Calculations ORNL Report September, 2021
Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... ORNL Report August, 2021
Application of Markov Chain Monte Carlo Methods for Uncertainty Quantification in Inverse Transport Problems... Journal August, 2021
Progress on the reevaluation and validation of the n+ 233 U neutron cross sections... Journal August, 2021
Updates to Improve the Evaluated Nuclear Data of Copper Isotopes in the Resolved and Unresolved Resonance Regions ORNL Report July, 2021
Thermal neutron scattering measurements and modeling of yttrium-hydrides for high temperature moderator applications Journal July, 2021