Abstract

The purpose of this study is to evaluate the radiation effects depending on the size of the damage of cask when the outer shield of a spent nuclear fuel transportation cask is damaged by impact due to sabotage. Neutron and gamma-ray intensities and spectra were calculated using the ORIGEN module of the SCALE 6.2.4 code package (W. A. Wieselquist et al., 2020), and the equivalent dose rates were calculated using the MCNP6.2 code (C. J Werner, et al., 2017).The ABAQUS code was used to assess the degree of the opening of the cask lid due to external impact, and in the case of radiation source leakage, the dose assessment was performed by assuming a maximum of 6% damage to the nuclear fuel assemblies based on overseas experimental cases.

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