Bruce B Bevard Manager, NRC Projects Office Contact BEVARDBB@ORNL.GOV All Publications Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod An Historical Review of DOE's Attempt to Site a Monitored Retrievable Storage Facility in Oak Ridge, Tennessee, Between 1985 ... 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 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 A: Full-Length Rod Heat Treatments Sister Rod Destructive Examinations (FY23) Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests... Sister Rod Destructive Examinations (FY22) Appendix J: Leaching of High Burnup Used Nuclear Fuel in Deionized Water Sister Rod Destructive Examinations (FY22) Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests... Sister Rod Destructive Examinations (FY22) New Radiochemical Assay Experiments to Improve the Validation Basis for High Burnup Fuel Visualization of an Integrated Waste Management Concept of Operations in a Virtual Environment Metallography Examination and Hardness Measurements of High-Burnup Spent Nuclear Fuel Claddings During Simulated Drying Conditions Nuclide Inventory Validation: Radiochemical Assay Data Quality and Modeling Challenges in Benchmark Models Development... Sister Rod Destructive Examinations (FY21) Appendix F: Cyclic Integrated Reversible-Bending Fatigue Tests Sister Rod Destructive Examinations (FY21) Sister Rod Destructive Examinations (FY21) Appendix J: Leaching of High Burnup Used Nuclear Fuel in De-ionized Water 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 Fracture toughness evaluations for spent nuclear fuel dry storage canister welds and spent nuclear fuel clad-pellet structures 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 F: Cyclic Integrated Reversible-Bending Fatigue Tests 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 ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division SCALE
