Mathieu Dupont Research Staff Member Contact DUPONTMN@ORNL.GOV All Publications Design of Critical Experiments Involving Graphite elements at the IPEN/MB-01 Plate-Type Core Integral Experiment Request 554: CED-2 Summary Report Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies SCALE 6.3 Validation: Radiation Shielding ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels Experiments to Measure the Effect of Tantalum on Critical Systems... USE OF SCALE MAVRIC RADIATION TRANSPORT CALCULATIONS FOR THE DESIGN OF A SUBCRITICAL ASSEMBLY AT OAK RIDGE NATIONAL LABORATORY Review of Available Critical Experiments and Critical Experiments Facilities to Perform High-Assay Low-Enriched Uranium Fuel Transport Validation for Advanced Reactor Deployment Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Current Overview of Neutron Moderator Thermal Scattering Kernels for HALEU-Fueled Advanced Reactors Neutron Absorber Plate Characterization Plan for Criticality Experiments Design Using the Oak Ridge Subcritical Assembly for Gamma Ray Measurements Critical Experiments Targeting the Epithermal/Intermediate Cross Sections of Tantalum IMPACT OF RECENT ENDF NUCLEAR DATA ON BURNUP CREDIT CRITICALITY SAFETY ANALYSES Preliminary Design of Critical Experiments Involving Commercially available B4C Neutron Absorber Plates with Low-Enriched UO2 fuel Horizontal Split-Table Conceptual Design to Support Advanced Reactor Validation Needs Proposed Subcritical Assembly for Nuclear Criticality Safety Training at the Oak Ridge National Laboratory Current Progress of the Final Design of a Subcritical Assembly at the Oak Ridge National Laboratory... Health Physics Research Reactor Criticality Accident Alarm System Benchmark Overview SCALE 6.2.4 Validation: Radiation Shielding Integral Experiment Request 554 CED-1 Summary Report... Evaluation of Oak Ridge National Laboratory Health Physics Research Reactor Operation Data for Critical Benchmark Creation Update of the Nuclear Criticality Slide Rule: Review of the Estimation of the Number of Fissions... Pagination Current page 1 Page 2 Next page ›› Last page Last » 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
