FeCrAl fuel/clad chemical interaction in light water reactor environments

Qu, Haozheng J.; Higgins, Maria; Abouelella, Hamdy; Cappia, Fabiola; Burns, Jatuporn; He, Lingfeng; Massey, Caleb; Harp, Jason; Field, Kevin G.; Howard, Richard; Umretiya, Rajnikant V.; Hoffman, Andrew K.; Wharry, Janelle P.; Rebak, Raul B.

doi:10.1016/j.jnucmat.2023.154717

FeCrAl fuel/clad chemical interaction in light water reactor environments

Journal Article · Fri Sep 08 04:00:00 EDT 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154717· OSTI ID:2000268

^[1]; ^[2]; ^[1]; Cappia, Fabiola ^[3]; Burns, Jatuporn ^[3]; He, Lingfeng ^[4]; Massey, Caleb ^[5]; ^[5]; Field, Kevin G. ^[6]; ^[5]; ^[1]; Hoffman, Andrew K. ^[1]; ^[7]; Rebak, Raul B. ^[1]

GE Global Research, Schenectady, NY (United States)
Pennsylvania State Univ., University Park, PA (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
North Carolina State University, Raleigh, NC (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Univ. of Michigan, Ann Arbor, MI (United States)
Purdue Univ., West Lafayette, IN (United States)

This article investigates the fuel-cladding chemical interaction (FCCI) behavior of two commercial FeCrAl alloys, APMT composition (Fe-21Cr-5Al-3Mo wt.%) and C35M (Fe-13Cr-5Al-2Mo-0.2Si-0.03Y wt.%), after neutron irradiation. “H-cup” diffusion multiples of FeCrAl alloys and ceramic UO₂ fuel were irradiated at a temperature of ~300 °C to a total estimated burnup of 26 GWd/tHM. Post-irradiation Examination results demonstrate the excellent degradation resistance of FeCrAl alloys as accident tolerant fuel (ATF) cladding materials in light water reactor conditions. The study concludes that there was no irradiation-induced defects observed in either of the two commercial FeCrAl claddings. The formation of amorphous Al/U mixed oxide was observed at the fuel-clad interface, which can serve as a tritium permeation barrier and protect against potential chemical attack from the fuel. Finally, the study attributed the formation of amorphous Al/U mixed oxide to the low temperature and limited time of neutron irradiation. APMT forms more distinct Cr and Cr-Fe intermetallic at the FeCrAl-UO₂ interface than C35M due to the higher bulk Cr:Al ratio.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES). Scientific User Facilities (SUF)

Grant/Contract Number:: AC05-00OR22725; NE0009047

OSTI ID:: 2000268

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: 154717 Vol. 587; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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