Rose A Montgomery Senior Research Staff and Group Leader Contact montgomeryra@ornl.gov | 865.576.1381 All Publications Sister Rod Destructive Examinations (FY22)... Sister Rod Destructive Examinations (FY21)... Sister Rod Destructive Examinations (FY20)... Sister Rod Destructive Test Results (FY19) Enhanced material identification via momentum-integrated muon scattering tomography 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 C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests 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 Key results from examinations of seven high burnup pressurized water reactor spent nuclear fuel rods 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 Sister Rod Destructive Examinations (FY23) Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests Image reconstruction algorithm for momentum dependent muon scattering tomography A New Momentum-Integrated Muon Tomography Imaging Algorithm Sister Rod Destructive Examinations (FY22) Appendix J: Leaching of High Burnup Used Nuclear Fuel in Deionized Water Sister Rod Destructive Examinations (FY22) Appendix I: SNF Aerosols Released During Rod Fracture Sister Rod Destructive Examinations (FY22) Appendix E: Mechanical Testing Sister Rod Destructive Examinations (FY21) Appendix C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests... Sister Rod Destructive Examinations (FY22) Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests Sister Rod Destructive Examinations (FY22) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrogen The Effect of Vacuum Drying on Hydride Reorientation in High-Burnup Nuclear Fuel Claddings for Extended Dry Storage Computational modeling and validation of a modified Marple cascade impactor Evaluation of Fuel Rod Fatigue During Spent Fuel Transportation Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID 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 User Facilities Oak Ridge Leadership Computing Facility