Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 467, Issue -, Pages 703-716Publisher
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2015.10.019
Keywords
Nuclear grade; Wrought; FeCrAl; Accident tolerant fuel cladding; LWR
Funding
- U.S. Department of Energy's Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle RD program
- Scientific User Facilities Division, Office of Basic Energy Sciences, U.S. Department of Energy
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Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys with enhanced accident tolerance. Ferritic alloys with sufficient chromium and aluminum additions can exhibit significantly improved oxidation kinetics in high-temperature steam environments when compared to zirconium-based alloys. In the first phase, a set of model FeCrAl alloys containing 10-20Cr, 3-5Al, and 0-0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FeCrAlY alloys. It was found that the tensile properties were insensitive to the alloy compositions studied; however, the steam oxidation resistance strongly depended on both the chromium and the aluminum contents. The second phase development focused on strengthening Fe-13Cr-5Al with minor alloying additions of molybdenum, niobium, and silicon. Combined with an optimized thermo-mechanical treatment, a thermally stable microstructure was produced with improved tensile properties at temperatures up to 741 degrees C. (C) 2015 Elsevier B.V. All rights reserved.
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