Tara Pandya Radiation Transport Group Lead Contact 806.438.7961 | PANDYATM@ORNL.GOV All Publications VERA 4.1 Release Notes Effect of Fission Source Spectrum on Monte Carlo Calculation of Ex-Core Quantities High-Fidelity Ex-core Capabilities in VERA VeraShift I/O Optimization for Ex-core Calculations with VERA 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 Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems... Nuclide Depletion Capabilities in the Shift Monte Carlo Code Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines Nuclide depletion capabilities in the Shift Monte Carlo code Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines 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 NUCLIDE DEPLETION CAPABILITIES IN THE SHIFT MONTE CARLO CODE... FW/CADIS-Ω: AN ANGLE-INFORMED HYBRID METHOD FOR DEEP-PENETRATION RADIATION TRANSPORT Capabilities, Implementation, and Benchmarking of Shift, a Massively Parallel Monte Carlo Radiation Transport Code... Hot Zero Power Reactor Calculations Using the Insilico Code Shift: A Massively Parallel Monte Carlo Radiation Transport Package THREE-DIMENSIONAL DISCRETE ORDINATES REACTOR ASSEMBLY CALCULATIONS ON GPUS Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 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 Nuclear Data, Criticality Safety, and Radiation Transport Section Radiation Transport Group SCALE User Facilities
