Andrew Worrall Director, Nuclear Energy Programs Contact WORRALLA@ORNL.GOV All Publications Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview Molten Salt Reactor Neutronics and Fuel Cycle Modeling and Simulation with SCALE Transitioning to a Thorium Fuel Cycle with Molten Salt Reactors... Transition to a Thorium-based Fuel Cycle - Choices, Challenges, and Opinions Identification of fuel cycle simulator functionalities for analysis of transition to a new fuel cycle... Defining a Research Agenda for Advanced Fuel Cycle Safeguards: A Focus on Thorium ... Analysis of Operational and Safety Performance for Candidate Accident Tolerant Fuel and Cladding Concepts ASSESSMENT AND BENCHMARKING WITH ORION AND CYCLUS FOR US FUEL CYCLE OPTIONS High-Fidelity Modeling of Spent Fuel Assemblies for Advanced NDA Instrument Testings... Generating Cross Sections for ORION Fuel Cycle Models Assessment and Benchmarking with ORION and CYCLUS for U.S. Fuel Cycle Options Safeguards Considerations for Thorium Fuel Cycles Modeling and Simulation of the Start-Up of a Thorium-Based Molten Salt Reactor Analysis of Key Safety Metrics of Thorium Utilization in LWRs Fuel Cycle Performance of Thermal Spectrum Small Modular Reactors Standardized Verification of Fuel Cycle Modeling Analysis of Key Safety Metrics of Thorium Utilization in LWRs 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 An Approach for Assessing Development and Deployment Risks in the DOE Fuel Cycle Options Evaluation and Screening Study... Transition Analysis of Promising U.S. Future Fuel Cycles Using ORION Thorium-Based Fuel Cycles Explained for Safeguards Practitioners... Sustainable Thorium Nuclear Fuel Cycles: A Comparison of Intermediate and Fast Neutron Spectrum Systems... Demonstration of a Full-core Reactivity Equivalence for FeCrAl Enhanced Accident Tolerant Fuel in BWRs... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division National Center for Computational Sciences Oak Ridge Leadership Computing Facility Technology Integration Group
