Ian Greenquist Nuclear Fuels Analyst Contact GREENQUISTIT@ORNL.GOV All Publications Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study Sensitivity and uncertainty of the IFR-1 BISON benchmark Compatibility of Zircaloy-4 in eutectic PbSn and PbBiSn liquid metals High-burnup boiling water reactor steady-state operating conditions and fuel performance analysis High-Burnup BWR LOCA Burst Analysis Framework Development and Demonstration... Fuel Performance Calculations of Tagged UO¬2 MiniFuel Disks NEAMS Burnup Extension Accomplishments and Remaining Modeling Gaps UO2-Liquid Metal Suspension Fuel Concept: Alloy Selection and Depletion Calculations Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions Phase Field Sintering Simulations of Tagged UO2... Multiscale Modeling of Radiation Damage in UO2 under Accelerated Burnup Conditions Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions Coupled Neutronics, Thermal Hydraulics, and Fuel Performance Simulations of a Natural Circulation Based SMR Development of Microreactor Automated Control System (MACS): Surrogate Plant-level Modeling and Control Algorithms Integration Accelerated fission rate irradiation design, pre-irradiation characterization, and adaptation of conventional PIE methods for U-10Mo and U-17Mo Assessment of the Effect of Prototypic High-Burnup Operating Conditions of Fuel Fragmentation, Relocation, and Dispersal Susceptibility Coupled Neutronic and Thermal Hydraulic Analysis of a Natural Circulation Based Small Modular Reactor (SMR) using VERA-CS... Metallic Fuel Performance Benchmarks for Versatile Test Reactor Applications 25-Pin metallic fuel performance benchmark case based on the EBR-II X430 experiments series Sensitivity and Uncertainty of the IFR-1 BISON Benchmark Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment Streamlining the Coupling of BISON and Dakota Through the NEAMS Workbench BISON metallic fuels benchmark simulations based on the X430 experiments Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » 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
