Rose Montgomery Distinguished Research Staff Contact 865.576.1381 | MONTGOMERYRA@ORNL.GOV All Publications Sister Rod Destructive Examinations (FY22) Sister Rod Destructive Examinations (FY21) Sister Rod Destructive Examinations (FY20) Sister Rod Destructive Test Results (FY19) Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod DEFORMATION MECHANISMS AND ANNEALING EFFECTS IN 17X17 PWR FUEL RODS UNDER PINCH LOADING CONDITIONS... Radiation Source Localization Algorithm in the Pedestrian Radiation Portal Monitor Simulation Framework for Cosmic Ray Muon Impact on Radiation Portal Monitors Sister Rod Destructive Examinations (FY23) Appendix E2: Four-point bend fractured specimen images Enhanced material identification via momentum-integrated muon scattering tomography Sister Rod Destructive Examinations (FY22) Appendix E: Mechanical Testing... Sister Rod Destructive Examinations (FY23) Sister Rod Destructive Examinations (FY23) Appendix D: Fission Gas, Fuel Burnup, and Fuel Isotopic Measurements Sister Rod Destructive Examinations (FY23) Appendix C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests Sister Rod Destructive Examinations (FY23) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrogen Momentum informed muon scattering tomography for monitoring spent nuclear fuels in dry storage cask Sister Rod Destructive Examinations (FY23) Appendix A: Full-Length Rod Heat Treatments Sister Rod Destructive Examinations (FY23) Appendix J: Leaching of High Burnup Used Nuclear Fuel in Deionized Water Key results from examinations of seven high burnup pressurized water reactor spent nuclear fuel rods... Sister Rod Destructive Examinations (FY23) Appendix I: SNF Aerosols Released During Rod Fracture Nuclear material accountancy using momentum-informed muon scattering tomography Sister Rod Destructive Examinations (FY23) Appendix G: CIRFT Uncertainty Calculations... Sister Rod Destructive Examinations (FY23) Appendix H: Instron Uncertainty Calculations Metallographic examinations and hydrogen measurements of high-burnup spent nuclear fuel cladding... Assessing the release, transport, and retention of radioactive aerosols from hypothetical breaches in spent fuel storage canisters Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID LinkedIn Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Integrated Fuel Cycle Section Used Fuel and Nuclear Material Disposition Group
