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An Open Analysis Platform with In-Situ Machine Vision for Electron Microscopy Final Technical Report

FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development

Fracture Toughness Characterization of Generation II FeCrAl Alloys after\~ 18 dpa Irradiation

Assessment of deformation mechanisms in neutron-irradiated accident-tolerant fecral alloys via in situ mechanical testing and TEM analysis

Iron-chromium-aluminum (FeCrAl) alloys are promising as an accident-tolerant fuel cladding for loss-of-coolant accident scenarios; however, limited data are available on the acting deformation mechanisms for this class of materials after neutron …

Hydrothermal corrosion of coatings on silicon carbide in boiling water reactor conditions

SiC/SiC ceramic matrix composites are an attractive material for use as accident tolerant fuel cladding. However, despite its resistance to corrosion in high-temperature steam, SiC is known to dissolve in high-temperature water, necessitating the use …

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

Accelerated irradiation testing of miniature fuel specimens

Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR

Ex-situ and in-situ determination of alpha prime phase formation/dissolution in high-cr ferritic alloys using small-angle neutron scattering.

Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1.1) Prepared for U.S. Department of Energy Nuclear Technology R\&D Advanced Fuels Campaign FY18 version author(s): Kevin G. Field 1 FY17 version author(s)