Hydrothermal Corrosion of Latest Generation of FeCrAl Alloys for Nuclear Fuel Cladding

BS Nagothi, H Qu, W Zhang, RV Umretiya, E Dolley… - Materials, 2024 - mdpi.com
BS Nagothi, H Qu, W Zhang, RV Umretiya, E Dolley, RB Rebak
Materials, 2024mdpi.com
After the Fukushima nuclear disaster, the nuclear materials community has been vastly
investing in accident tolerant fuel (ATF) concepts to modify/replace Zircaloy cladding
material. Iron–chromium–aluminum (FeCrAl) alloys are one of the leading contenders in this
race. In this study, we investigated FA-SMT (or APMT-2), PM-C26M, and Fe17Cr5. 5Al over
a time period of 6 months in simulated BWR environments and compared their performance
with standard Zirc-2 and SS316 materials. Our results implied that water chemistry along …
After the Fukushima nuclear disaster, the nuclear materials community has been vastly investing in accident tolerant fuel (ATF) concepts to modify/replace Zircaloy cladding material. Iron–chromium–aluminum (FeCrAl) alloys are one of the leading contenders in this race. In this study, we investigated FA-SMT (or APMT-2), PM-C26M, and Fe17Cr5.5Al over a time period of 6 months in simulated BWR environments and compared their performance with standard Zirc-2 and SS316 materials. Our results implied that water chemistry along with alloy chemistry has a profound effect on the corrosion rate of FeCrAl alloys. Apart from SS316 and Zirc-2 tube specimens, all FeCrAl alloys showed a mass loss in hydrogen water chemistry (HWC). FA-SMT displayed minimal mass loss compared to PM-C26M and Fe17Cr5.5Al because of its higher Cr content. The mass gain of FeCrAl alloys in normal water chemistry (NWC) is significantly less when compared to Zirc-2.
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