Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding

Rebak, Raul B.; Jurewicz, Timothy B.; Larsen, Michael; Yin, Liang

doi:10.1016/j.corsci.2022.110156

Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding

Journal Article · Fri Apr 01 00:00:00 EDT 2022 · Corrosion Science

DOI:https://doi.org/10.1016/j.corsci.2022.110156· OSTI ID:1845036

Rebak, Raul B.; Jurewicz, Timothy B.; Larsen, Michael; Yin, Liang

Not Available

Research Organization:: General Electric Co., Schenectady, NY (United States)

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: NE0009047

OSTI ID:: 1845036

Alternate ID(s):: OSTI ID: 1977036

Journal Information:: Corrosion Science, Journal Name: Corrosion Science Journal Issue: C Vol. 198; ISSN 0010-938X

Publisher:: ElsevierCopyright Statement

Country of Publication:: United Kingdom

Language:: English

References (10)

Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment Kim, Ho-Sub; Lee, Hyeon Bae; Chen, Junjie Corrosion Science, Vol. 151 https://doi.org/10.1016/j.corsci.2019.02.012	journal	May 2019
Effect of zinc addition scenarios on general corrosion of Alloy 690 in borated and lithiated water at 330 °C Lim, Dong-Seok; Jeon, Soon-Hyeok; Bae, Byung Joon Corrosion Science, Vol. 189 https://doi.org/10.1016/j.corsci.2021.109627	journal	August 2021
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
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
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
Characterization of oxide layers formed on type 316 stainless steel exposed to the simulated PWR primary water environment with varying dissolved hydrogen and zinc concentrations Lee, Hyeon Bae; Chen, Junjie; Meng, Shu Journal of Nuclear Materials, Vol. 556 https://doi.org/10.1016/j.jnucmat.2021.153193	journal	December 2021
Effect of zinc injection on the electrochemical behavior and crack growth rate of a 316 L stainless steel in simulated primary coolant of pressurized water reactors Arjmand, Farzin; Zhang, Lefu; Zhang, Yuting Materials Characterization, Vol. 177 https://doi.org/10.1016/j.matchar.2021.111177	journal	July 2021
Corrosion mitigation in coolant systems in nuclear power plants Chajduk, Ewelina; Bojanowska-Czajka, Anna Progress in Nuclear Energy, Vol. 88 https://doi.org/10.1016/j.pnucene.2015.11.011	journal	April 2016
Iron-chrome-aluminum alloy cladding for increasing safety in nuclear power plants Rebak, Raul B. EPJ Nuclear Sciences & Technologies, Vol. 3 https://doi.org/10.1051/epjn/2017029	journal	January 2017

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Zinc water chemistry reduces dissolution of FeCrAl for nuclear fuel cladding

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References (10)

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