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The Radiation Dose Assessment Based on the Neutron Shield Material in Spent Fuel Transfer Casks

Donghee Lee
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  • URLhttps://db.koreascholar.com/Article/Detail/435943
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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
2024 춘계학술발표회 논문요약집 (2024.05)
p.107
한국방사성폐기물학회 (Korean Radioactive Waste Society)
키워드
Spent fuel transfer casksNeutron shieldRadiation dose assessment
저자
  • Donghee Lee(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
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