Keith C Bledsoe Senior R&D Staff Contact 865.574.8602 | bledsoekc@ornl.gov All Publications Radiation Hot Spot Seasonal Variation on UF6 Cylinders Radiation Dose Impact of an Overpack Storage Configuration for Plutonium Disposition Fractionation of UF6 and daughter progeny in storage cylinders from external heating Samoa Updater: An Application of the Levenberg-Marquardt Method to Update Delfic Predictions Using Field Measurements Application of Markov Chain Monte Carlo Methods for Uncertainty Quantification in Inverse Transport Problems... Fission Product Yield Data Adjustment in a Prototype Version of TSURFER Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor Application of Markov Chain Monte Carlo for Uncertainty Quantification in Quantitative Imaging Problems... Uncertainty Analysis for Neutron Active Interrogation Calculations... Application of Polynomial Chaos Expansion in Inverse Transport Problems with Neutron Multiplication Measurements and Multiple Unknowns Determining Physical Parameters of Shielded Uranium using Gamma Spectroscopy and the DiffeRential Evolution Adaptive Metropolis (DREAM) Method Application of Polynomial Chaos Expansion in Inverse Transport Problems with Neutron Multiplication Measurements and Multiple Unknowns Determining physical parameters of shielded uranium using gamma spectroscopy and the DiffeRential Evolution Adaptive Metropol... Solving Inverse Transport Problems with Neutron Multiplication Measurements and Improved Differential Evolution Uncertainty Quantification for Quantitative Imaging Holdup Measurements Application of the DiffeRential Evolution Adaptive Metropolis (DREAM) Method for Uncertainty Quantification in Inverse Transport Problems Improved Differential Evolution Implementation for Solving Inverse Transport Problems Application of Generalized Linear Least-Squares for Uncertainty Quantification in Inverse Transport Problems... Benchmark On Sensitivity Calculation (Phase III)... The Effect of U-234 Content on the Neutronic Behavior of Uranium Systems... A comparison of the Covariance Matrix Adaptation Evolution Strategy and the Levenberg–Marquardt method for solving multidimensional inverse transport problems Evaluation of HEU-Beryllium Benchmark Experiments to Improve Computational Analysis of Space Reactors... Key Links Curriculum Vitae ORCID 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
