Rose A Montgomery Senior Research Staff and Group Leader Contact montgomeryra@ornl.gov | 865.576.1381 All Publications Sister Rod Destructive Examinations (FY22) Appendix I: SNF Aerosols Released During Rod Fracture 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 Experimental Investigation of Aerosol Release from Spent Nuclear Fuel Fractures... Using Cosmic Ray Muons to Assess Geological Characteristics in the Subsurface Metallography Examination and Hardness Measurements of High-Burnup Spent Nuclear Fuel Claddings During Simulated Drying Conditions The Mechanical Response of High Burnup 17x17 PWR Fuel Rods Under Bending... Sister Rod Destructive Examinations (FY21) Appendix G: CRIFT Uncertainty Calculations... Sister Rod Destructive Examinations (FY20) Appendix I: SNF Aerosols Released During Rod Fracture... Sister Rod Destructive Examinations (FY21) Appendix J: Leaching of High Burnup Used Nuclear Fuel in De-ionized Water Sister Rod Destructive Examinations (FY21) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrog... Sister Rod Destructive Examinations (FY21) Appendix E Mechanical Testing... Sister Rod Destructive Examinations (FY21) Appendix H: Instron Uncertainty Calculations Sister Rod Destructive Examinations (FY21) Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests... Sister Rod Destructive Examinations (FY21) Appendix C: Rod Internal Pressure, Void Volume, and Gas Transmission Tests... Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod... Finite Element Evaluation of Spent Nuclear Fuel for Dynamic Impact Load Cases Experimental Plan for Commercial SNF Degradation in Repository Environments with a Focus on Fracture Matrix Degradation Fracture toughness evaluations for spent nuclear fuel dry storage canister welds and spent nuclear fuel clad-pellet structure... Fatigue Test Result for High Burnup Pressurized Water Reactor Rods... Drop impact tester development for spent nuclear fuel vibration integrity study... Sister Rod Destructive Examinations (FY20) Appendix A: Full Length Fuel Rod Heat Treatments (FHT)... Sister Rod Destructive Examinations (FY20) Appendix D, Fission Gas Analysis, Fuel Rod Burnup and Isotopic Measurements... Sister Rod Destructive Examinations (FY20), Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests... Pagination First page « First Previous page ‹‹ Page 1 Current 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