This study examined the safety of nuclear spent-fuel (NSF) transport casks against accidental puncture events. Finite element analyses were conducted according to the accident conditions in NUREG-1536 and RG 7.8, which specify 1-m parallel and vertical drops on a rigid rod that has 15-cm diameter and 20-cm height. We focused on the safety evaluation of the cask body, baskets, and canister based on ASME BPVC Section III, and evaluated whether these elements would undergo excessive fracture or puncture.

Abstract
 1. 서 론
 2. 연구내용 및 방법
 3. 결 론
 참고문헌

• 김승필(울산과학기술원 석박통합과정) | Kim Seungpil
• 신명수(울산과학기술원) | Shin Myoungsu
• 손동성((주) 한스코) | Sohn Dong-Seong
• 권혁주((주) 한스코) | Kwon Hyukjoo