Dorothea A Wiarda Contact wiardada@ornl.gov | 865.299.9028 All Publications 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 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 On the creation of the new ENDF/B-VIII.0 Covariance Library for SCALE Applications with AMPX... Improvement Of The SCALE-XSPROC Capability For High-Temperature Gas-Cooled Reactor Analysis Multigroup cross section library and processing for the CASL VERA neutronic simulators Bayesian Monte-Carlo Evaluation Framework for Cross Sections Nuclear Data and Integral Benchmark Experiments 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... SCALE/Sampler Sensitivity Indices... Activation Study of Isotopically Enriched Samples During Neutron TOF Measurements... Development of the multigroup cross section library for the CASL neutronics simulator MPACT: Method and procedure... The SCALE/AMPX multigroup cross section processing for fast reactor analysis... Nuclear Data and Benchmarking Program: Nuclear Data and Covariance Assessment, ENDF/B-VIII.0 Covariance Data Development and Testing Report 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
