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...
Guardat en:
| Autors principals: | , , , , , , , |
|---|---|
| Format: | Artigo |
| Idioma: | Chinês |
| Publicat: |
Science Press
2024-09-01
|
| Col·lecció: | He jishu |
| Matèries: | |
| Accés en línia: | http://www.hjs.sinap.ac.cn/zh/article/doi/10.11889/j.0253-3219.2024.hjs.47.090601/ |
| Etiquetes: |
Sense etiquetes, Sigues el primer a etiquetar aquest registre!
|