Contact Information montgomeryra@ornl.gov 865.576.1381 orcid.org/0000-0002-8603-8936 LinkedIn Related 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 Rose A Montgomery Senior Research Staff and Group Leader Download CV All Publications Sister Rod Destructive Test Results (FY19)... Sister Rod Destructive Examinations (FY20)... Sister Rod Destructive Examinations (FY21)... The Mechanical Response of High Burnup 17x17 PWR Fuel Rods Under Bending... Metallography Examination and Hardness Measurements of High-Burnup Spent Nuclear Fuel Claddings During Simulated Drying Condi... 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... Sister Rod Destructive Examinations (FY21) Appendix G: CRIFT Uncertainty Calculations... Sister Rod Destructive Examinations (FY20) Appendix I: SNF Aerosols Released During Rod Fracture... 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... Drop impact tester development for spent nuclear fuel vibration integrity study... Fatigue Test Result for High Burnup Pressurized Water Reactor Rods... Sister Rod Destructive Examinations (FY20), Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests... Sister Rod Destructive Examinations (FY20) Appendix B: Segmentation, Defueling, Metallography, and Total Cladding Hydrogen Me... Sister Rod Destructive Examinations (FY20) Appendix C: Rod internal Pressure, void volume, and gas transmission tests... Sister Rod Destructive Examinations (FY20) Appendix E, Mechanical Testing... 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... Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last »
