Aaron Wysocki Staff Research Scientist Contact WYSOCKIAJ@ORNL.GOV All Publications Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows Mechanistic Modeling of Departure from Nucleate Boiling under Transient Scenarios WHOLE CORE CRUD-INDUCED POWER SHIFT SIMULATIONS USING VERA Validation and Benchmarking of CTF For Single- And Two-Phase Flow Using VIPRE-01 Molten Salt Reactor Simulations using MPACT-CTF Validation of CTF Droplet Entrainment and Annular/Mist Closure Models using Riso Steam/Water Experiments... Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: core design and safety analysis Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: motivation and overview... Development and Assessment of CTF for Pin-resolved BWR Modeling Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis Potential Impact of Cladding Wettability on LWR Transient Progression Reactivity Initiated Accident Simulation to Inform Transient Testing of Candidate Advanced Cladding Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview THE MODELING OF ADVANCED BWR FUEL DESIGNS WITH THE NRC FUEL DEPLETION CODES PARCS/PATHS Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Page 2 Current page 3 Key Links Curriculum Vitae Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Advanced Reactor Engineering and Development Section Advanced Reactor Systems Group
