Abstract
Bentonite-based buffer for high-level radioactive waste (HLW) disposal is expected to fill the interstitial spaces around buffer materials by its swelling deformation. This study performs one-dimensional model tests simulating the relation around the buffer and evaluates the self-sealing capability of the buffer quantitatively. It also investigates the applicability of the theoretical equations for evaluating the swelling characteristics of a bentonite-based buffer, first proposed by Komine and Ogata, to analysis of the self-sealing capability by comparing the calculated and experimentally obtained results. Furthermore, this study has shown the design flow for specifications of bentonite-based buffer from the viewpoint of self-sealing capability.
