Dorothea Wiarda Contact WIARDADA@ORNL.GOV All Publications 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 SCALE Resonance Parameter Sensitivity Coefficient Calculations Bayesian optimization of generalized data Verification and Validation of the ENDF/B-VII.1 v4.3m1 MPACT 51-group Cross Section Library The AMPX/SCALE Multigroup Cross-Section Processing for Fast Reactor Analysis ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data Advancing the Fork detector for quantitative spent nuclear fuel verification Advancing the Fork detector for quantitative spent nuclear fuel verification Generalized Reich-Moore R -matrix approximation ENDF/B-VIII.0 Testing With AMPX and SCALE A New Method for Generating Probability Tables in the Unresolved Resonance Region Automatic Coarse Energy Group Structure Optimization by Minimizing Reaction Rate Differences for the SCALE and CASL Code Syst... Development of the CASL-VERA V4.2m5 MPACT 51-group Libraries for ENDF/B-VII.0 and VII.1... Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries NCSP FY 2015 AMPX Annual Report Multigroup Data Processing for the Embedded Self-Shielding Method in SCALE... New Features of the ORIGEN Transmutation Code in SCALE 6.2 CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND AMPX: A Modern Cross Section Processing System for Generating Nuclear Data Libraries Development and Testing of Neutron Cross Section Covariance Data for SCALE 6.2... Monte Carlo Capabilities of the SCALE Code System... Development of a New 47-Group Library for the CASL Neutronics Simulators... Pagination First page « First Previous page ‹‹ Page 1 Current 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
