William B.J. Marshall Senior R&D Staff Contact marshallwj@ornl.gov | 865.576.7872 All Publications Neutronic Benchmarking of Small Fast Gas-Cooled Systems SCALE Lattice Physics Code Assessments of Accident Tolerant Fuel ENDF/B-VIII.0 Augmented Covariance Data: The first iteration... Impact of the ENDF/B-VIII.0 Library on Advanced Reactor Simulations Bias Between ENDF/B-VIII and ENDF/B-VII.1 for LEU Pin Array Systems... Sensitivity/Uncertainty Comparison Study: Oak Ridge National Laboratory Results... VALIDATION OF KENO V.A AND KENO-VI IN SCALE 6.3 BETA 3 USING ENDF/B-VII.1 AND ENDF/B-VIII LIBRARIES... ASSESSMENT OF NORMALITY FOR CRITICALITY SAFETY BIAS AND BIAS UNCERTAINTY CALCULATION 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 Overview of the Recent BWR Burnup Credit Project at Oak Ridge National Laboratory 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 W... A Method for Performing k?ff Validation of As-Loaded Criticality Safety Calculations Using UNF-ST&DARDS... 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 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... A Testing Trifecta: Data, Codes, and Evaluations... Benchmark Model Temperatures Incorporated into DICE... Estimating Computational Biases for Criticality Safety Applications with Few Neutronically Similar Benchmarks... Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Nuclear Criticality Safety Group SCALE