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Database on Performance of Neutron Irradiated FeCrAl Alloys

The present report summarizes and discusses the database on radiation tolerance for Generation I, Generation II, and commercial FeCrAl alloys. This database has been built upon mechanical testing and microstructural characterization on selected …

FeCrAl alloys for accident tolerant fuel cladding in light water reactors

The goal of the U.S. Department of Energy (DOE) Accident Tolerant Fuel Program (ATF) for light water reactors (LWR) is to identify alternative fuel system technologies to further enhance the safety of commercial nuclear power plants. An ATF fuel …

Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions

Life extension of light water reactors will expose austenitic internal core components to irradiation damage levels beyond 100 displacements per atom (dpa), leading to profound microstructural evolution and consequent degradation of macroscopic …

Post-deformation examination of specimens subjected to SCC testing

Recent Advances in Analytical Electron Microscopy for Irradiated Materials

Status of FeCrAl ODS Irradiations in the High Flux Isotope Reactor

FeCrAl oxide-dispersion strengthened (ODS) alloys are an attractive sub-set alloy class of the more global FeCrAl material class for nuclear applications due to their high-temperature steam oxidation resistance and hypothesized enhanced radiation …

Status of Post Irradiation Examination of FCAB and FCAT Irradiation Capsules

Status Report on Irradiation Capsules Containing Welded FeCrAl Specimens for Radiation Tolerance Evaluation

Submission of FeCrAl Feedstock for Support of AFC ATR- ­ 2 Irradiations

The Analysis of the General Performance and Mechanical Behavior of Unirradiated FeCrAl Alloys Before and After Welding