Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

2015/10/23 by Y. Yamamoto, Yukinori Yamamoto, Bruce A. Pint +8 · 3 citations
Materials Science · Engineering · #Nuclear Materials and Properties #Fusion materials and technologies #Nuclear reactor physics and engineering

paper · doi:10.1016/j.jnucmat.2015.10.019

Citations

• Ferritic/martensitic steels for next-generation reactors
• Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions

Cited by

• Accident tolerant fuel cladding development: Promise, status, and challenges
• Current status of materials development of nuclear fuel cladding tubes for light water reactors
• Vacancy Diffusion Across FeCrAl Alloy Composition Space for Accident-Tolerant Fuel Cladding