Dave J Kropaczek Contact kropaczekdj@ornl.gov | 865.576.5093 All Publications Coupled neutronics and species transport simulation of the Molten Salt Reactor Experiment... Parameters of Neutron Diffusion Equation for Temperature Effect of MSRE Heat and Mass Transfer Coefficients in the Molten Salt Reactor Experiment Differences in high burnup fuel management strategies to minimize FFRD and increase economic viability... Subchannel Methods Development for Modeling of Light Water Reactors at Oak Ridge National Laboratory Advanced two-phase subchannel method via non-linear iteration... Assessing UN Neutronic and Fuel Performance for Extended Cycle Lengths... Digital Twins for Nuclear Power Plants and Facilities MOOGLE: A Multi-Objective Optimization tool for three-dimensional nuclear fuel assembly design... A Novel Method for Controlling Crud Deposition in Nuclear Reactors Using Optimization Algorithms and Deep Neural Network Base... CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pre... Verification and Validation of the Alternative Nonlinear Two-phase Subchannel (ANTS) Code Bypass Flow Model Implementation for VERA BWR The pursuit of net-positive sustainability for industrial decarbonization with hybrid energy systems... Final Summary Report on the Feasibility and the Benefits of the Advanced Nuclear Fuel Pellet Designs with Radially Varying Fu... Quantum Physics Inspired Methods for Two-Batch PWR Loading Pattern Optimization... The Role of Hybrid Energy Systems in Decarbonizing Industry: A Carbon Handprint–Based Case Study... Parallel Simulated Annealing with Embedded Machine Learning and Multifidelity Models for Reactor Core Design... APPLICATION OF DEEP LEARNING NETWORKS TO SURROGATE MODELLING OF CRUD DEPOSITION... Analysis of Approximations in Modeling of BWR Bundle Void Distributions... Roadmap for thermal property measurements of Molten Salt Reactor systems... Development of the VERA Quality Assurance Program... CASL FY18 Annual Report... Inference of Crud Model Parameters from Plant Data On the validity of the dilute gas assumption for gap conductance calculations in nuclear fuel performance codes Pagination Current page 1 Page 2 Next page ›› Last page Last » Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division CASL NE Modeling & Simulation Hub