Goran Arbanas Research and Development Staff - Nuclear Data Contact 865.574.4984 | ARBANASG@ORNL.GOV All Publications Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety Total thermal neutron cross section measurements of hydrogen dense polymers from 0.0005–20 eV Total thermal neutron cross section measurements of yttrium hydride from 0.0005 - 3 eV Bayesian Optimization Framework for Imperfect Data or Models Extension of SCALE/Sampler’s Sensitivity Analysis... RESONANCE PARAMETER ADJUSTMENT BASED ON INTEGRAL EXPERIMENTS... Exploration of direct neutron capture with covariant density functional theory inputs Structures of exotic 131,133Sn isotopes and effect on r-process nucleosynthesis... Covariance Matrix of a Double-Differential Doppler-broadened Elastic Scattering Cross Section... Evaluation of the Chromium Resonance Parameters Including Resonance Parameter Covariance... Astrophysical reaction rates for Ni-58,Ni-60(n,gamma) from new neutron capture cross section measurements... Statistical Properties of Kawai-Kerman-McVoy T-matrix... Resonance Region Covariance Analysis Method and New Covariance Data for Th-232, U-233, U-235, U-238, and Pu-239... Low-fidelity Covariance Project... Porosity in nuclear graphite and its impact on nuclear reactor science and criticality safety applications Recognizing Unrecognized Sources of Uncertainty (USU) in Nuclear Data Development of Nuclear Data Measurements Capabilities at the Spallation Neutron Source Neutronics Study of HTR-10: Impact of Graphite Porosity Representation in ENDF/B-VIII.1 TSLs Assessing criticality implications of porosity misrepresentation in ENDF/B-VIII.1 graphite TSLs and small angle neutron scattering in nuclear graphite Effective R-Matrix Parameterizations for Nuclear Data R-matrix Resolved Resonance Region Evaluation of 140,142Ce STATUS REPORT OF JOINT RPI/ORNL NCSP TASK FOR THERMAL NEUTRON TOTAL CROSS SECTION MEASUREMENTS Modernization efforts for the R-Matrix code SAMMY Comparative Analysis of Confidence Metrics for Nuclear Criticality Safety Bayesian Monte Carlo Evaluation Framework for Imperfect Nuclear Data Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » 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 Nuclear Data Group SCALE
