Effectiveness of the neutron-shield nanocomposites for a dual-purpose cask of Bushehr's WatereWater Energetic Reactor (VVER) 1000 nuclear-power-plant spent fuels

In order to perform dry interim storage and transportation of the spent-fuel assemblies of the BushehrNuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shieldmaterials for the dual-purpose cask was analyzed through a set of calculations carried out using theMonte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recentlydeveloped materials of epoxy/clay/B4C and epoxy/clay/B4C/carbon fiber was less than the allowableradiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. Byutilization of epoxy/clay/B4C instead of an ethylene glycol/water mixture, the dose rates on the sidesurface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%. KCI Citation Count: 1