Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3 Journal November, 2021
VERA Transient Capability to Support ATF/High Burnup Fuel/HALEU Conversion ORNL Report November, 2021
LWR DECAY HEAT ANALYSIS WITH SCALE 6.3 AND ENDF/B-VIII.0 NUCLEAR DATA LIBRARIES Conference Paper November, 2021
Reactor Cell Neutron Dose for the Molten Salt Breeder Reactor Conceptual Design... Journal November, 2021
Flow boiling transient critical heat flux tests with stainless steel and FeCrAl: Transient correlation implementation, model calibration, and sensitivity analysis Journal November, 2021
Extension of the NEAMS workbench to parallel sensitivity and uncertainty analysis of thermal hydraulic parameters using Dakota and Nek5000 Journal October, 2021
UNF-ST&DARDS: A UNIQUE TOOL FOR SPENT NUCLEAR FUEL CHARACTERIZATION AND LONG-TERM FUEL DATABASE MANAGEMENT Conference Paper October, 2021
