Post irradiation examinations of FeCrAl cladding in PWR conditions

Colldeweih, A. W.; Petersen, P. G.; Matos, M. D.; Stockwell, J. A.; Hansen, R. S.; Kamerman, D. W.; Lutz, D.; Cappia, F.

doi:10.1016/j.jnucmat.2024.155402

Title: Post irradiation examinations of FeCrAl cladding in PWR conditions

Journal Article · 31 December 2024 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2024.155402 · OSTI ID:2446537

Colldeweih, A. W.; Petersen, P. G.; Matos, M. D.; Stockwell, J. A.; Hansen, R. S.; Kamerman, D. W.; Lutz, D.; Cappia, F.

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

OSTI ID:: 2446537

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 603; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: Netherlands

Language:: English

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Determination of the hoop fracture properties of unirradiated hydrogen-charged nuclear fuel cladding from ring compression tests Martin-Rengel, M. A.; Gómez Sánchez, F. J.; Ruiz-Hervías, J. Journal of Nuclear Materials, Vol. 436, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.01.311	journal	May 2013
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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
On α′ precipitate composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys Reese, Elaina R.; Bachhav, Mukesh; Wells, Peter Journal of Nuclear Materials, Vol. 500 https://doi.org/10.1016/j.jnucmat.2017.12.036	journal	March 2018
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
Resumption of water capsule reactivity-initiated accident testing at TREAT Folsom, Charles P.; Schulthess, Jason L.; Kamerman, David W. Nuclear Engineering and Design, Vol. 413 https://doi.org/10.1016/j.nucengdes.2023.112509	journal	November 2023
Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys Kobayashi, Satoru; Takasugi, Takayuki Scripta Materialia, Vol. 63, Issue 11 https://doi.org/10.1016/j.scriptamat.2010.08.015	journal	November 2010
Influence of recrystallization on phase separation kinetics of oxide dispersion strengthened Fe–Cr–Al alloy Capdevila, C.; Miller, M. K.; Pimentel, G. Scripta Materialia, Vol. 66, Issue 5 https://doi.org/10.1016/j.scriptamat.2011.11.003	journal	March 2012
Irradiation-enhanced α′ precipitation in model FeCrAl alloys Edmondson, P. D.; Briggs, S. A. Scripta Materialia, Vol. 116 https://doi.org/10.1016/j.scriptamat.2016.02.002	journal	April 2016
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