Effect of the redox potential on the general corrosion behavior of industrial nuclear alloys

Rebak, Raul B.; Yin, Liang; Zhang, Wanming; Umretiya, Rajnikant V.

doi:10.1016/j.jnucmat.2023.154257

Effect of the redox potential on the general corrosion behavior of industrial nuclear alloys

Journal Article · Sat Apr 01 00:00:00 EDT 2023 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2023.154257· OSTI ID:1909296

; Yin, Liang; Zhang, Wanming;

Not Available

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: NE0009047

OSTI ID:: 1909296

Alternate ID(s):: OSTI ID: 2418375

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 576; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

References (11)

Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding Rebak, Raul B.; Jurewicz, Timothy B.; Larsen, Michael Corrosion Science, Vol. 198 https://doi.org/10.1016/j.corsci.2022.110156	journal	April 2022
Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water Ning, Fangqiang; Wang, Xiang; Yang, Ying Journal of Materials Science & Technology, Vol. 70 https://doi.org/10.1016/j.jmst.2020.07.026	journal	April 2021
Uniform corrosion of FeCrAl alloys in LWR coolant environments Terrani, K. A.; Pint, B. A.; Kim, Y. -J. Journal of Nuclear Materials, Vol. 479 https://doi.org/10.1016/j.jnucmat.2016.06.047	journal	October 2016
Accident tolerant fuel cladding development: Promise, status, and challenges Terrani, Kurt A. Journal of Nuclear Materials, Vol. 501 https://doi.org/10.1016/j.jnucmat.2017.12.043	journal	April 2018
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding Raiman, Stephen S.; Field, Kevin G.; Rebak, Raul B. Journal of Nuclear Materials, Vol. 536 https://doi.org/10.1016/j.jnucmat.2020.152221	journal	August 2020
Corrosion behavior of ferritic FeCrAl alloys in simulated BWR normal water chemistry Wang, Peng; Grdanovska, Slavica; Bartels, David M. Journal of Nuclear Materials, Vol. 545 https://doi.org/10.1016/j.jnucmat.2020.152744	journal	March 2021
Uniform corrosion of FeCrAl cladding tubing for accident tolerant fuels in light water reactors Yin, Liang; Jurewicz, T. B.; Larsen, M. Journal of Nuclear Materials, Vol. 554 https://doi.org/10.1016/j.jnucmat.2021.153090	journal	October 2021
Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan Sakamoto, K.; Miura, Y.; Ukai, S. Journal of Nuclear Materials, Vol. 557 https://doi.org/10.1016/j.jnucmat.2021.153276	journal	December 2021
Microstructure and tensile behavior of powder metallurgy FeCrAl accident tolerant fuel cladding Huang, Shenyan; Dolley, Evan; An, Ke Journal of Nuclear Materials, Vol. 560 https://doi.org/10.1016/j.jnucmat.2022.153524	journal	March 2022
Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding Motta, Arthur T.; Couet, Adrien; Comstock, Robert J. Annual Review of Materials Research, Vol. 45, Issue 1 https://doi.org/10.1146/annurev-matsci-070214-020951	journal	July 2015
Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments Rebak, Raul B.; Larsen, Michael; Kim, Young-Jin Corrosion Reviews, Vol. 35, Issue 3 https://doi.org/10.1515/corrrev-2017-0011	journal	August 2017

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