Feasibility assessment of using external neutron and gamma radiation measurements for monitoring the state of fuel assemblies in dry storage casks

Abstract

This study assesses the feasibility of using external neutron and gamma flux measurements to detect the state of spent fuel assemblies inside a sealed cask. Several Monte-Carlo simulations were performed to evaluate the neutron and gamma flux distribution outside the sidewall of a cask with all intact fuel assemblies and a cask with one damaged fuel assembly, mimicking a fuel assembly with expanded rods and fuel relocation. The evaluation was performed for different positions of the damaged fuel assembly and different storage times. The results show that in case the damaged fuel assembly is located near the inner wall of the cask, it can be detected by both of the radiation modes. The detection of the inner damaged fuel assemblies, however, can be feasible only by the external neutron flux.