Hydride growth mechanism in zircaloy-4: Investigation of the partitioning of alloying elements
The long-term safety of water-based nuclear reactors relies in part on the reliability of zirconium-based nuclear fuel cladding. Yet the progressive ingress of hydrogen during service makes zirconium alloys subject to delayed hydride cracking. Here, we use a combination of electron back-scattered di...
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Published in | Materialia Vol. 15; p. 101006 |
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Main Authors | , , , , , , |
Format | Journal Article |
Language | English |
Published |
Elsevier B.V
01.03.2021
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Subjects | |
Online Access | Get full text |
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