Characterization of Long-Term, In-Reactor Zircaloy-4 Corrosion Coupons and the Impact of Flux, Fluence, and Temperature on Oxide Growth, Stress Development, Phase Formation, and Grain Size

Characterization of Long-Term, In-Reactor Zircaloy-4 Corrosion Coupons and the Impact of Flux, Fluence, and Temperature on Oxide Growth, Stress Development, Phase Formation, and Grain Size

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Veröffentlicht in:International Symposium on Zirconium in the Nuclear Industry (19. : 2019 : Manchester) Zirconium in the nuclear industry
1. Verfasser: Ensor, Brendan (VerfasserIn)
Weitere Verfasser: Lucadamo, Gene (VerfasserIn), Seidensticker, John R. (VerfasserIn), Bajaj, Ram (VerfasserIn), Cai, Zhonghou (VerfasserIn), Motta, Arthur T. (VerfasserIn)
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Sprache:eng
Veröffentlicht: 2021
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