In this paper, as the transport cask was moved in the reactor, the structural integrity on the cask had to be evaluated in the normal transport condition. The drop height of the cask was determined by the weight of the cask in the normal transport condition by regulations about assessment test. It was determined that the drop height of the cask was 1.2 m by regulations. The velocity of the drop impact was calculated to perform the drop impact analysis by the principle of the conservation of energy. Using results of the simulation about the drop impact analysis, the structural integrity assessment on the transport cask was performed by ASME Boiler and Pressure Vessel Code.

• 양태호(Member, Korea Atomic Energy Research Institute) | Tae-Ho Yang Corresponding Author
• 홍진태(Korea Atomic Energy Research Institute) | Jin-tae Hong
• 연건휘(Chungnam National University) | Korea Atomic Energy Research Institute