Simulation of Helium Flow Visualization Apparatus for Studies of Blanket Cooling in Fusion Reactors Journal June, 2024
Analysis and design of fast flow liquid Li divertor for fusion nuclear science facility (FNSF) using coupled plasma boundary and LM MHD/heat transfer codes* Journal April, 2024
Assessment of thermal and radiation induced creep in the dual cooled lead lithium blanket Journal April, 2024
Preliminary Assessment of Additively Manufactured Cooling Channel Performance for Helium-Cooled Blanket Concepts Journal April, 2024
Impact of breech geometry and propellant flow on the release of large pellets for the ITER disruption mitigation system Journal February, 2024
Characterization of the MHD flow and pressure drop in the access ducts of a liquid metal fusion blanket... Journal February, 2024
Modifications to the JET Shattered Pellet Injector to Optimize Disruption Mitigation Experiments for Supporting ITER’s DMS Design Journal February, 2024
INTEGRATED PLASMA AND ENGINEERING DESIGN AND ASSESSMENT FOR TOKAMAK REACTOR COMPONENTS... Conference Paper October, 2023
IMPACT OF BREECH GEOMETRY AND PROPELLANT FLOW ON THE RELEASE OF LARGE PELLETS FOR THE ITER DISRUPTION MITIGATION SYSTEM Conference Paper October, 2023
Qualification and Commissioning of Helium Flow Loop Experiment for Blanket Design Measurements Journal April, 2023
