Development and validation of models for fuel rod oxidation and hydrogen pick-up behaviors in pressurized water reactor
BackgroundDuring the long-term operation of a nuclear reactor, the contact between zirconium alloy cladding and cooling water results in oxidation reactions and hydrogen uptake-induced embrittlement behavior, which deteriorates the thermal and mechanical properties of the cladding, posing a threat t...
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| Hlavní autoři: | , , , , , , , |
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| Médium: | Artigo |
| Jazyk: | Chinês |
| Vydáno: |
Science Press
2024-09-01
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| Edice: | He jishu |
| Témata: | |
| On-line přístup: | http://www.hjs.sinap.ac.cn/zh/article/doi/10.11889/j.0253-3219.2024.hjs.47.090601/ |
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