William (B.J.) Marshall Distinguished R&D Staff Contact MARSHALLWJ@ORNL.GOV All Publications Criticality Safety Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations THE INFLUENCE OF CHANGES IN NUCLEAR COVARIANCE DATA ON THE CALCULATION OF Ck FOR HIGHLY ENRICHED URANIUM SOLUTION SYSTEMS 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 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 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 Nuclear Data and Benchmarking Program: Nuclear Data and Covariance Assessment, ENDF/B-VIII.0 Covariance Data Development and Testing Report Nuclear Data and Benchmarking Program: Nuclear Data Performance Assessment for Advanced Reactors A Testing Trifecta: Data, Codes, and Evaluations A Case Study in the Application of TSUNAMI-3D - Part 3, Continuous Energy - Iterative Fission Probability Method Sensitivity Calculations for Systems with Fissionable Reflector Materials Using TSUNAMI 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 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 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 Impact of Assembly-Specific Conditions on BWR Burnup Credit Critical Experiment Design Phase 1 Report for Integral Request 441 Determination of Critical Experiment Correlations for Experiments Involving Arrays of Low-Enriched Fuel Rods Determination of Critical Experiment Correlations for Experiments Involving High-Enriched Uranium Solutions 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
