Jesse Brown Nuclear Data Scientist Contact BROWNJM@ORNL.GOV All Publications Unresolved resonance parameter evaluation and uncertainty quantification of n+181Ta reactions Validating Automated Resonance Evaluation with Synthetic Data Automated Resonance Fitting for Nuclear Data Evaluation Recognizing Unrecognized Sources of Uncertainty (USU) in Nuclear Data A new Ta-181 neutron resolved resonance region evaluation... Proceedings for the Workshop on Applied Nuclear Data Activities 2024 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 Nuclide Inventory Validation: Effect of Nuclear Data Libraries Effective R-Matrix Parameterizations for Nuclear Data Photonuclear Physics in SCALE Methodology for physics-informed generation of synthetic neutron time-of-flight measurement data Optimal Chloride Salt Mixture for a Fusion Blanket... STATUS REPORT OF JOINT RPI/ORNL NCSP TASK FOR THERMAL NEUTRON TOTAL CROSS SECTION MEASUREMENTS New Measurements to Resolve Discrepancies in Evaluated Model Parameters of 181 Ta Bayesian Monte Carlo Evaluation of Imperfect (n, 233U) Data and Model Advanced Modeling and Simulation Methods for Evaluation of Thermal Neutron Scattering Materials... Modernization efforts for the R-Matrix code SAMMY Parameterization of Direct and Doorway Processes in R-Matrix Formalism Zirconium Nuclear Data Campaign: Measurement of 90Zr (n, γ) cross section 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 CERBERUS:A Multi-Purpose Spectrometer and Alignment Station at SNS... ORNL Neutron Cross Section Measurements of 90Zr Generalized Bayesian Framework for Evaluation of Integral Benchmark Experiments... Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links 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
