Safety evaluation of nuclear spent-fuel transport casks in puncture events

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