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James Travis Dixon

Travis Dixon

4501/4505 Operations Engineer

Contact

DIXONJT@ORNL.GOV

All Publications

METHOD FOR EXPOSING IRRADIATED FUEL CLADDING TO RAPID THERMAL TRANSIENTS
Sister Rod Destructive Examinations (FY23) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrogen
Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium...
Irradiation of ultrasonic sensors and adhesive couplants for application in light water reactor primary loop piping and compo...
Mechanical Properties of Neutron-Irradiated Zr-Alloy Weldments (Batch #2)
Sister Rod Destructive Examinations (FY22) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrogen
Milestone Report on Microstructure of Irradiated Sensors and Coupling Adhesive Bonds
Sister Rod Destructive Examinations (FY21) Appendix B: Segmentation, Defueling, Metallographic Data and Total Cladding Hydrog...
Characterization of Fuel and Cladding In and Near the Pellet-Pellet Gap of a High-Burnup Pressurized Water Reactor Fuel Rod
Experimental Evaluation of Deformation and Fracture Mechanisms in Highly Irradiated Austenitic Steels
Sister Rod Destructive Examinations (FY20) Appendix B: Segmentation, Defueling, Metallography, and Total Cladding Hydrogen Me...
Sister Rod Destructive Test Results (FY19)

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