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Comparison of Hydride Embrittlement of Zircaloy-4 and Zr-Nb Alloy Cladding Tubes

Sangbum Kim, Joo-Hee Kang, Youho Lee
  • 언어ENG
  • URLhttps://db.koreascholar.com/Article/Detail/425447
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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
2021 춘계학술논문요약집 (2021.06)
p.83
한국방사성폐기물학회 (Korean Radioactive Waste Society)
키워드
Zr alloyHydride embrittlementDuctile-to-brittle transitionSpent nuclear fuel management
저자
  • Sangbum Kim(Department of Nuclear Engineering Seoul National University, 1, Gwanak-ro, Gwanak-gu, Seoul 08826, Republic of Korea)
  • Joo-Hee Kang(Korea Institute of Materials Science, 797, Changwon-daero, Seongsan-gu, Changwon-si, Gyeongsangnam-do 51508, Republic of Korea)
  • Youho Lee(Department of Nuclear Engineering Seoul National University, 1, Gwanak-ro, Gwanak-gu, Seoul 08826, Republic of Korea)
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