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Y Yamamoto

Design of Experiment for Irradiation of Welded Candidate Fe-Cr-Al Alloys
Experimental Plan and Irradiation Target Design for FeCrAl Embrittlement Screening Tests Conducted Using the High Flux Isotope Reactor
Optimization of Nuclear Grade FeCrAl Fuel Cladding for Light Water Reactors
Radiation Tolerance of Neutron-Irradiated Model Fe-Cr-Al Alloys
FY-14 FCRD Milestone: M3FT-14OR0202232 FCRD Advanced Fuels Campaign (AFC) Level 3 Milestone Report Letter Report Documenting Progress of Second Generation ATF FeCrAl Alloy Fabrication
Stability of Model Fe-Cr-Al Alloys Under The Presence of Neutron Radiation
Letter report documenting identifying billets and alloys fabricated for distribution to program, FY13 FCRD milestone report, M3FT-13OR0202291, ORNL/LTR-2013/322

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