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Richard Howard

FeCrAl fuel/clad chemical interaction in light water reactor environments
Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Fracture Toughness Characterization of Generation II FeCrAl Alloys after\~ 18 dpa Irradiation
Current status of FeCrAl alloys as an accident tolerant cladding alloy class for commercial light water reactors
Evaluation of the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys, ORNL/TM-2015/518 M2FT-15OR02302243
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

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