摘要：To meet safety requirements for underground storage of high-level nuclear waste, engineered barriers are anintegral part of a modern defense-in-depth concept and therefore have to be considered in interaction with the host rock.This study presents preliminary results for the load behaviorof a canister made of pressure-less sintered silicon carbide(SSiC), which forms the main retention barrier for the fissionproducts in a new multi-layer waste package design denominated as TRIPLE C. This means a three-fold enclosure strategy, spreading the functionalities to three different ceramicbarriers: first the porous potting compound surrounding eachsingle fuel rod in the container, second the solid containerwall of SSiC and third the over-pack of carbon concrete. Besides all the advantages a potential drawback of ceramics ingeneral is their brittleness. Therefore, the behavior of SSiCstructural components under static and dynamic loading hasto be investigated. First results for a small model canister indicate that static loading will not create any relevant damage,even if stresses are extremely high and highly anisotropicon a canister all-around embedded. First dynamic simulations indicate that, under very unfavorable circumstances, themodel canister can experience tensile stresses bigger than itstensile strength. Also, point loading may cause damage tothe canister under certain conditions. Based on the performedcalculations, the SSiC canister design will be optimized together with the carbon concrete over-pack, so that mechanical damage of main retention barrier can be excluded evenunder extreme static and dynamic conditions in a final repository.
