논문 상세보기

Investigation of Dissolution Behavior of SrO in Molten LiCl Salt at 923 K

Dokyu Kang, James T. M. Amphlett, Eun-Young Choi, Sang-Eun Bae, Sungyeol Choi
  • 언어ENG
  • URLhttps://db.koreascholar.com/Article/Detail/425441
모든 회원에게 무료로 제공됩니다.
한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
2021 춘계학술논문요약집 (2021.06)
p.74
한국방사성폐기물학회 (Korean Radioactive Waste Society)
키워드
Used nuclear fuelPyroprocessingHighly heat-generating fission products
저자
  • Dokyu Kang(Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 34141, Republic of Korea)
  • James T. M. Amphlett(Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 34141, Republic of Korea)
  • Eun-Young Choi(Korea Atomic Energy Research Institute, 111, Daedeok-daero 989beon-gil, Yuseong-gu, Daejeon 34057, Republic of Korea)
  • Sang-Eun Bae(Korea Atomic Energy Research Institute, 111, Daedeok-daero 989beon-gil, Yuseong-gu, Daejeon 34057, Republic of Korea)
  • Sungyeol Choi(Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 34141, Republic of Korea)
인용하기
양식 선택
언어 선택
로그인