Thermal Behaviors of Nuclear Fuel Samples and Cladding Materials by Using In-Situ High-Temperature XRD

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)

한국방사성폐기물학회 (Korean Radioactive Waste Society)

1. Introduction
2. Experimental section
3. Results & discussions
Acknowledgement

저자

Sang Ho Lim(Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea, Department of Radiochemistry & Nuclear Nonproliferation, University of Science and Technology, Daejeon, Republic of Korea)
Jeongmook Lee(Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea)
Dong Woo Lee(Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea)
Young-Sang Youn(Department of Chemistry, Yeungnam University, Gyeongbuk, Republic of Korea)
Jong-Yun Kim(Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea, Department of Radiochemistry & Nuclear Nonproliferation, University of Science and Technology, Daejeon, Republic of Korea)
Tae-Hyung Kim(Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea)
Junghwan Park(Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea)

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