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

Design of Experiment for Irradiation of Welded Candidate Fe-Cr-Al Alloys

Development of a robust modeling tool for radiation-induced segregation in austenitic stainless steels

Experimental Plan and Irradiation Target Design for FeCrAl Embrittlement Screening Tests Conducted Using the High Flux Isotope Reactor

Fabrication Control Plan for Mo-L ATF Test Speicmens to be Irradiated in the ATR

First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

Optimization of Nuclear Grade FeCrAl Fuel Cladding for Light Water Reactors

Proceedings of the Third Meeting of the OECD-NEA Expert Group on Accident Tolerant Fuels for LWRs, 3-5 March 2015, OECD-NEA HQ

Recent Advances in Understanding Radiation Damage In Reactor Cavity Concrete

License renewal up to 60 years and the possibility of subsequent license renewal to 80 years has resulted in a renewed focus on long-term aging of materials at nuclear power plants (NPPs) including concrete. Large irreplaceable sections of most …