Mathieu N Dupont Research Staff Member Contact dupontmn@ornl.gov | 865.341.2198 All Publications Neutron Absorber Plate Characterization Plan for Criticality Experiments Design Using the Oak Ridge Subcritical Assembly for Gamma Ray Measurements 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... Expansion of the ORNL VALID Library Update of the Nuclear Criticality Slide Rule Calculations: Plutonium systems – Delayed Fission Gamma Update of the Nuclear Criticality Slide Rule Calculations: Plutonium Systems – Delayed Fission Gamma... A Subcritical Assembly for Training and Education Use at the Oak Ridge National Laboratory... Horizontal Split Table Conceptual Design for Advanced Reactor Validation Evaluation of Oak Ridge National Laboratory Health Physics Research Reactor Operation Data for Criticality Accident Alarm System Benchmark Creation Design of Temperature Dependent Critical Experiments with SPRF/CX... Criticality Accident Alarm System Shielding Benchmark: Integral Experiment Request 498, Critical Engineering Decision 2 Repor... Overview of the 2020 SCALE 6.2.4 Validation Report for Radiation Shielding Applications* KENO-VI Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS6) with Fulcrum... KENO V.a Primer: Performing Calculations using SCALE’s Criticality Safety Analysis Sequence (CSAS5) with Fulcrum... Updated Primers Generated for SCALE 6.2 for KENO V.a and KENO-VI Sulfur Pellets Responses to a Bare and Steel Reflected Pulse of the Oak Ridge National Laboratory Health Physics Research Reactor 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
