William (B.J.) Marshall Distinguished R&D Staff Contact 865.576.7872 | MARSHALLWJ@ORNL.GOV All Publications Initial Application of TSUNAMI for Validation of Advanced Fuel Systems DETAILED DESIGN OF AN EPITHERMAL/INTERMEDIATE CRITICAL EXPERIMENT USING THE SANDIA NATIONAL LABORATORIES CRITICAL FACILITY Overview of the Recent BWR Burnup Credit Project at 91°µÍø VALIDATION OF KENO V.A AND KENO-VI IN SCALE 6.3 BETA 3 USING ENDF/B-VII.1 AND ENDF/B-VIII LIBRARIES Validation of keff Calculations for Extended BWR Burnup Credit Calculations User Experiences with ICSBEP Distributed Sensitivity Data Profiles with the SCALE Sensitivity and Uncertainty Methods as of Winter 2019 A Method for Performing k?ff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS Initial Investigations of the Criticality Safety Validation Basis for HA-LEU Transportation Preliminary TSUNAMI Assessment of the Impact of Accident Tolerant Fuel Concepts on Reactor Physics Validation Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors Nuclear Data and Benchmarking Program: Nuclear Data and Covariance Assessment, ENDF/B-VIII.0 Covariance Data Development and Testing Report Sensitivity Calculations for Systems with Fissionable Reflector Materials Using TSUNAMI A Testing Trifecta: Data, Codes, and Evaluations A Case Study in the Application of TSUNAMI-3D - Part 3, Continuous Energy - Iterative Fission Probability Method Benchmark Model Temperatures Incorporated into DICE Estimating Computational Biases for Criticality Safety Applications with Few Neutronically Similar Benchmarks The Case for and Against a Gadolinium Bias in SCALE: Opening Arguments Validation of KENO V.a and KENO-VI in SCALE 6.2.2 using ENDF/B-VII.0 and ENDF/B-VII.1 Libraries Enhanced Engineering Analyses with Visualization of Geometry and Mesh-Based Data in Fulcrum Determination of Critical Experiment Correlations for Experiments Involving High-Enriched Uranium Solutions Development of Criticality Safety Validation Guidance for NRC-Regulated Activities... Template Engine Applied to Rapid Modeling As-Loaded Criticality Margin Assessment of Dual Purpose Canisters Using UNF-ST&DARDS ENDF/B-VIII.0 Testing With AMPX and SCALE A Burnup Credit Approach for Margin Estimation of Loaded Boiling Water Reactor Canisters in UNF-ST&DARDS Pagination First page « First Previous page ‹â¶Ä¹ … Page 3 Current page 4 Page 5 … Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae
