Criticality safety study for loss of single fuel rod from WH 14 type fuel

It is expected that the storage capacity of the SFP in the Nuclear Power Plant (NPP) will be saturated in 2024, starting from Kori NPP. Thus it is necessary to transport SNF from NPP site to intermediate storage facilities. The objective of this study, the effect of single failed fuel rod is to confirm on the criticality safety whether is significant. As a result, the ℏk values(baseline ± fuel rod loss position) of 14OFA was largest. The ℏk values resulting from single rod removal in the basket-cell model range from -0.00129 for rods near the edge of the lattice to +0.00170 for rods near the center. Thus, it is confirmed that the study for the consequences of potential fuel failure is significant because fuel assemblies are designed to be undermoderated, and the loss of a fuel pin from the lattice causes a local area of higher moderation, which can increase k_eff