1. Introduction
2. Experimental
    2.1 Selection of representative spent fuel
    2.2 Creep evaluation model
    2.3 Computational Method
3. Result & Discussion
    3.1 Temperature decay
    3.2 Creep strain in dry storage condition
4. Conclusion
ACKNOWLEDGEMENT

• You-Jin Kang(Department of Nuclear Engineering, Hanyang University, 222 Wangsimni-ro, Seongdong-gu, Seoul 04763, Republic of Korea)
• Dongjun Lee(Department of Nuclear Engineering, Hanyang University, 222 Wangsimni-ro, Seongdong-gu, Seoul 04763, Republic of Korea)
• Wontak Lee(Department of Nuclear Engineering, Hanyang University, 222 Wangsimni-ro, Seongdong-gu, Seoul 04763, Republic of Korea)
• Eunho Choi(Department of Nuclear Engineering, Hanyang University, 222 Wangsimni-ro, Seongdong-gu, Seoul 04763, Republic of Korea)
• Sangtae Kim(Department of Nuclear Engineering, Hanyang University, 222 Wangsimni-ro, Seongdong-gu, Seoul 04763, Republic of Korea)
• Yong-Soo Kim(Department of Nuclear Engineering, Hanyang University, 222 Wangsimni-ro, Seongdong-gu, Seoul 04763, Republic of Korea)