Tara M Pandya Radiation Transport Group Lead Contact pandyatm@ornl.gov | 806.438.7961 All Publications Ex-Core Radiation Transport Modeling with VERA User Manual VeraShift Usability Updates for Production Releases of VERA for Ex-core Calculations Source Range Detector Response Modeling using VERA Coupled Deterministic and Monte Carlo Neutronics for Vessel Fluence Calculations... Optimization of processor allocation for domain decomposed Monte Carlo calculations... Watts Bar I Ex-Core Analyses using VERA Nuclide Depletion Capabilities in the Shift Monte Carlo Code... Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems... Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines... Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines Nuclide depletion capabilities in the Shift Monte Carlo code Modeling Parallel Efficiency for Discrete Ordinates Transport Calculations... AP1000 Benchmarking of VERA Neutronics Toolset... Flux Renormalization in Constant Power Burnup Calculations... Hot Zero Power Reactor Calculations Using the Insilico Code... FW/CADIS-Ω: AN ANGLE-INFORMED HYBRID METHOD FOR DEEP-PENETRATION RADIATION TRANSPORT... NUCLIDE DEPLETION CAPABILITIES IN THE SHIFT MONTE CARLO CODE... Capabilities, Implementation, and Benchmarking of Shift, a Massively Parallel Monte Carlo Radiation Transport Code... Hot Zero Power Reactor Calculations Using the Insilico Code THREE-DIMENSIONAL DISCRETE ORDINATES REACTOR ASSEMBLY CALCULATIONS ON GPUS... Shift: A Massively Parallel Monte Carlo Radiation Transport Package... Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem... Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem Massively Parallel, Three-Dimensional Transport Solutions for the k-Eigenvalue Problem Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Key Links Curriculum Vitae ORCID LinkedIn GitHub Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Radiation Transport Group SCALE User Facilities Oak Ridge Leadership Computing Facility