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

Nagothi, Bhavani Sasank; Qu, Haozheng; Zhang, Wanming; Umretiya, Rajnikant V.; Dolley, Evan; Rebak, Raul B.

doi:10.3390/ma17071633

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

Journal Article · 02 April 2024 · Materials

DOI: https://doi.org/10.3390/ma17071633 · OSTI ID:2333080

Nagothi, Bhavani Sasank; Qu, Haozheng; Zhang, Wanming;

; Dolley, Evan; Rebak, Raul B.

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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Sponsoring Organization:: USDOE

Grant/Contract Number:: NE0009047

OSTI ID:: 2333080

Alternate ID(s):: OSTI ID: 2471880

Journal Information:: Materials, Journal Name: Materials Journal Issue: 7 Vol. 17; ISSN 1996-1944; ISSN MATEG9

Publisher:: MDPI AGCopyright Statement

Country of Publication:: Switzerland

Language:: English

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