Joel McDuffee Group Leader, Irradiation Engineering Contact MCDUFFEEJL@ORNL.GOV All Publications High Flux Isotope Reactor Low-Enriched Uranium High Density Silicide Fuel Preliminary Design Update: System Transient Analysis Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731... Heat transfer optimization of uo2-mo fuel using genetic algorithms Thermal Optimization of UO2-Mo Fuel Using Sensitivity Analysis and Genetic Algorithms Simulation of natural circulation cartridge loop experiments and application to molten salt reactors Testing and Simulation of an Updated Cartridge Loop Vehicle Enhancement Concept Reactor Physics Studies to Support HFIR Upgrade Planning Activities Plutonium-238 Production Program Results, Implications, and Projections from Irradiation and Examination of Initial NpO2 Test Targets for Improved Production Neutron irradiation of tungsten in hydrogen environment at HFIR Design and Control of a Fueled Molten Salt Cartridge Experiment for the Versatile Test Reactor Conceptual design of HFIR irradiation experiment for material compatibility study on liquid Sn divertor... Single-phase, natural circulation annular flow measurements for cartridge loop irradiation experiments Wireless Instrumented RB Experiment Preliminary Design and Analysis Transient Testing of Natural Circulation Flow in Cartridge Experiments Neutron Irradiation of Alloy N and 316L Stainless Steel in Contact with a Molten Chloride Salt Design and Modeling of a Liquid-Fuel Salt Experiment for the Versatile Test Reactor... Flow Test Plan to Support the Development of Cartridge Loops in the Versatile Test Reactor... Design Studies for the Optimization of 238 Pu Production in NpO 2 Targets Irradiated at the High Flux Isotope Reactor A Review of Molten Salt Irradiation Experiments Compressible Metal Foils for Temperature Control During Irradiation... Examination of Corrosion Development in a Chloride Salt Irradiation Experiment PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determinat... Design and Analysis of a NPO2 Target for the Production of 238PU DESIGN OPTIMIZATION STUDIES FOR NPO2 TARGETS IRRADIATED IN THE HIGH FLUX ISOTOPE REACTOR Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Irradiation Engineering Group
