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Deformation Behavior in Neutron Irradiated Generation II FeCrAl Alloys for Accident Tolerant Fuel Cladding

Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor

Irradiation Testing of Accident Tolerant Fuel FeCrAl Cladding

Microstructural stability of irradiated Fe-Cr-Al alloys for fuel cladding applications.

ORNL/TM-2017/186 Rev.1 Handbook of FeCrAl Alloys for Nuclear Power Production Applications

FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power applications including accident tolerant fuel cladding, structural components for fast fission reactors, and as first wall and blanket structures for fusion …

Radiation Induced Segregation at Low Angle Grain Boundaries in Steels NSUF 2017 Milestone Report

Radiation Induced Segregation at Low Angle Grain Boundaries in Steels NSUF 2017 Milestone Report

Status of Wrought FeCrAl-UO2 Capsules Irradiated in the Advanced Test Reactor

Candidate cladding materials for accident tolerant fuel applications require extensive testing and validation prior to commercial deployment within the nuclear power industry. One class of cladding materials, FeCrAl alloys, is currently undergoing …

Synergies Between $\alpha$' and Cavity Formation in HT-9 Following High Dose Neutron Irradiation

Complementary Techniques for Quantification of $\alpha$' Phase Precipitation in Neutron-Irradiated Fe-Cr-Al Model Alloys

The substandard performance of Zircaloy LWR cladding materials under loss-of-coolant accident (LOCA) conditions has prompted the search for a more well-suited material for these conditions. Initial investigations of Fe-Cr-Al alloys have demonstrated …