Jeffrey J Powers Nuclear Reactor and Fuel R&D Staff Contact powersjj@ornl.gov | 865.576.9406 All Publications Assessment of Pellet-Clad Interaction Indicators in Watts Bar Unit 1, Cycles 1-3 Using VERA... Preliminary neutronics assessment of fully ceramic microencapsulated fuel in high-temperature gas-cooled reactors... Standardized Verification of Fuel Cycle Modeling... Core Design Characteristics of the Fluoride Salt-Cooled High Temperature Demonstration Reactor... Analysis of Key Safety Metrics of Thorium Utilization in LWRs Assessment of Pellet-Clad Interaction Indicators in Watts Bar Unit 1, Cycles 1-3 Using VERA Analysis of Key Safety Metrics of Thorium Utilization in LWRs Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Fuel Performance Calculations for FeCrAl Cladding in BWRs... Transition Analysis of Promising U.S. Future Fuel Cycles Using ORION... Assessment of Pellet-Clad Interaction Indicators in Watts Bar Unit 1 using the VERA Framework... Development of a Full-core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs... Demonstration of a Full-core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs... Sustainable Thorium Nuclear Fuel Cycles: A Comparison of Intermediate and Fast Neutron Spectrum Systems... Neutronic Analysis of Candidate Accident-Tolerant Cladding Concepts in Pressurized Water Reactors Neutronic Analysis of Candidate Accident-tolerant Cladding Concepts in Light Water Reactors... Liquid Fuel Molten Salt Reactors For Thorium Utilization... Fully Ceramic Microencapsulated (FCM) Fuel in FHRs: A Preliminary Reactor Physics Assessment... Fuel Cycle Assessment: Evaluation and Analyses using ORION for US Fuel Cycle Options... Safety Issues of Thorium Utilization in Commercial LWRs... Fully Ceramic Microencapsulated Fuels: Characteristics and Potential LWR Applications... An Inventory Analysis of Thermal-spectrum Thorium-fueled Molten Salt Reactor Concepts: Supporting U.S. Fuel Cycle Assessment... Reactor Physics Assessment of Alternate Cladding Materials... An Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reac... A Neutronic Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Pu/Np Burning in PWRs Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 Next page ›› Last page Last » Key Links ORCID