Charles F Weber Distinguished R&D Staff Contact 865.576.4475 | webercf@ornl.gov All Publications High-gradient magnetic separation of colloidal uranium oxide particles from soil components in aqueous suspensions... Effect of particle size on the capture of uranium oxide colloidal particles from aqueous suspensions via high-gradient magnetic filtration The effect of interfacial phenomena on gas solubility measurements in molten salts Engineering Evaluation of Barium Buildup in a Decayed CsCl Sealed Source and Potential Impact for Cesium Release from a Breached Source MSTAR2019 Code Description and User's Manual Density Calculations of Actinide Solutions using the Pitzer Method Transformative Data Analytics Capabilities for Nuclear Forensics and Safeguards Simulation of Undeclared Operations at Gas Centrifuge Enrichment Plants Using Quantile Comparisons to Classify Environmental Samples A composite position independent monitor of reactor fuel irradiation using Pu, Cs, and Ba isotope ratios Flexible classification with spatial quantile comparison and novel statistical features applied to spent nuclear fuel analysi... Classification of Forensic Measurements Using Multivariate Quantile Comparisons Sparse Bayesian Regression with Integrated Feature Selection for Nuclear Reactor Analysis Flexible classification with spatial quantile comparison and novel statistical features applied to spent nuclear fuel analysis A composite position independent monitor of reactor fuel irradiation using Pu, Cs, and Ba isotope ratios Sparse Bayesian Regression with Integrated Feature Selection for Nuclear Reactor Analysis... Rapid evaluation of particle properties using inverse SEM simulations penORNL: A PARALLEL MONTE CARLO PHOTON AND ELECTRON TRANSPORT PACKAGE USING PENELOPE... Simulation of Electron Probe Microanalysis for the Purposes of Automated Material Identification – Initial Evaluation of Available Monte Carlo Tools Generalized Modeling of Enrichment Cascades That Include Minor Isotopes... Development of Advanced Cermet Waste Forms... Inverse Solutions in Spectroscopic Analysis with Applications to Problems in Global Safeguards... Development of Advanced Cermet Waste Forms... Validation of Inverse Methods Applied to Forensic Analysis of Spent Fuel... Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel (NUREG/CR-6972, ORNL/TM-2008/015) Key Links Curriculum Vitae ORCID Organizations National Security Sciences Directorate Nuclear Nonproliferation Division Nonproliferation Engineering Science and Technologies Section Collection Science and Engineering Group
