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Abstract
The zirconium alloys used in nuclear industry include mainly ZreSn and ZreNb alloys ofdifferent chemical composition, microstructure and susceptibility to both hydrogendegradation and oxidation. The hypothetic nuclear accidents can create a real danger tothe Zr alloys and stability of parts made of these alloys, and especially such as loss ofcoolant accident (LOCA) and reactivity initiated accidents (RIA). The hydrogen degradationcan manifest itself in an appearance of hydride phases resulting in a substantial loss ofplasticity, an increase in ductileebrittle transition, sometimes in a decrease in mechanicalstrength. The oxidation can prevent the hydrogen entry but at high temperatures thecracking of the oxide layer can form the easy hydrogen diffusion channels. Based ona substantial number of tests made so far and well-known thermodynamic and kineticparameters, the general microstructure-dependent and temperature-dependent degradationmodel considering both hydrogen and oxidation could be elaborated.
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Details
- Category:
- Articles
- Type:
- artykuł w czasopiśmie wyróżnionym w JCR
- Published in:
-
INTERNATIONAL JOURNAL OF HYDROGEN ENERGY
no. 36,
pages 8619 - 8629,
ISSN: 0360-3199 - Language:
- English
- Publication year:
- 2011
- Bibliographic description:
- Zieliński A., Sobieszczyk S.: Hydrogen-enhanced degradation and oxide effects in zirconium alloys for nuclear applications// INTERNATIONAL JOURNAL OF HYDROGEN ENERGY. -Vol. 36, nr. iss. 14 (2011), s.8619-8629
- DOI:
- Digital Object Identifier (open in new tab) 10.1016/j.ijhydene.2011.04.002
- Verified by:
- Gdańsk University of Technology
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