Dorothea A Wiarda Research and Development Staff Contact 865.299.9028 | WIARDADA@ORNL.GOV All Publications Porosity in nuclear graphite and its impact on nuclear reactor science and criticality safety applications R-matrix analysis of n+natCl reactions up to 1.2 MeV Development of the ENDF/B-VII.1 and VIII.0 AMPX 61- and 258-Group Libraries for SCALE 7.0/Polaris LWR Analysis Recognizing Unrecognized Sources of Uncertainty (USU) in Nuclear Data Impact of Light Water Covariance on Integral Benchmarks Neutronics Study of HTR-10: Impact of Graphite Porosity Representation in ENDF/B-VIII.1 TSLs Effective R-Matrix Parameterizations for Nuclear Data Assessing criticality implications of porosity misrepresentation in ENDF/B-VIII.1 graphite TSLs and small angle neutron scattering in nuclear graphite Photonuclear Physics in SCALE Improvement of the SCALE-6.3/XSProc Pointwise Slowing-Down Capability with the Bound Thermal Scattering Data Including High F... Bayesian Monte Carlo Evaluation of Imperfect (n, 233U) Data and Model Parameterization of Direct and Doorway Processes in R-Matrix Formalism Modernization efforts for the R-Matrix code SAMMY Bayesian Optimization Framework for Imperfect Data or Models Extension of SCALE/Sampler’s Sensitivity Analysis... Bayesian Monte Carlo Evaluation Framework for Imperfect Nuclear Data Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis On the creation of the new ENDF/B-VIII.0 Covariance Library for SCALE Applications with AMPX... Bayesian Monte-Carlo Evaluation Framework for Cross Sections Nuclear Data and Integral Benchmark Experiments Multigroup cross section library and processing for the CASL VERA neutronic simulators Improvement of SCALE-XSPROC Multigroup Cross Section Processing Based on the CENTRM Pointwise Slowing Down Calculation Dr. Mark Williams' Three Contributions to Nuclear Data Covariance ENDF/B-VIII.0 Augmented Covariance Data: The first iteration NCSP Analytical Methods Subtask 3 & NCSP Nuclear Data Subtask 6: AMPX Development and Maintenance & SAMMY Modernization VALIDATION OF KENO V.A AND KENO-VI IN SCALE 6.3 BETA 3 USING ENDF/B-VII.1 AND ENDF/B-VIII LIBRARIES Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links 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
