Benjamin Collins Contact COLLINSBS2@ORNL.GOV All Publications VERA Core Simulator Methodology for PWR Cycle Depletion A lumped parameter method of characteristics approach and multigroup kernels applied to the subgroup self-shielding calculation in MPACT A Multigroup, Lumped Parameter MOC Method for Subgroup Self-Shielding in MPACT Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT... Extended Radial Reflector Modeling Capabilities in MPACT Implementation of a Red-Black SOR CMFD Solver in MPACT... CTF Parallel Performance Improvements... AP1000® PWR CYCLE 1 HFP DEPLETION SIMULATIONS WITH VERA-CS ... Assessment of Thermal Hydraulic Feedback Models A Hybrid Nodal P3/SP3 Axial Transport Solver for the MPACT 2D/1D Scheme Validation and Verification of the MPACT Code... Coupled MC21 and COBRA-IE Solution to VERA Core Physics Benchmark Problem #6... VERA Benchmarking Results for KRSKO Nuclear Power Plant Cycle 1... Application of Method of Manufactured Solutions in Neutron Transport Code... Simulation of CRUD Induced Power Shift using the VERA Core Simulator and MAMBA... VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12 Stability and accuracy of 3D neutron transport simulations using the 2D/1D method in MPACT Advanced Nodal P3/SP3 Axial Transport Solvers for the MPACT 2D/1D Scheme... Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS... Analysis of the BEAVRS Benchmark using MPACT HIGH FIDELITY MODELING OF PELLET-CLAD INTERACTION USING THE CASL VIRTUAL ENVIRONMENT FOR REACTOR APPLICATIONS VERA Core Simulator Methodology for PWR Cycle Depletion AP1000 PWR Startup Core Modeling and Simulation with VERA-CS (ANFM V) ASSESSMENT OF THE 2D/1D IMPLEMENTATION IN MPACT Improved Diffusion Coefficients for 2D/1D Axial Transport Solvers Applied to AP1000 PWR Startup Core Models... Pagination First page « First Previous page ‹‹ … Page 3 Page 4 Current page 5 Key Links Curriculum Vitae ORCID
