Development of overpack database

Taniguchi, Naoki ; Nakamura, Ario*

In geological disposal of high-level radioactive waste, overpack is required to prevent vitrified waste from the contacting groundwater with during a certain period of time. At present, the period is defined as 1000 years for complete containment and developments of technologies for design, manufacturing and quality assurance and researches for improving long-term performance have been carried out. Each R&D results have been published as a reports or journal papers by each individual institute. However, it is necessary to integrate these results so as to develop a practical knowledge base that would be useful for design of an overpack for a specific repository site, establishment of the codes and standards or other general purposes. Accordingly, we have been developing a database, which integrate R&D results on design concepts of overpack, technologies for design and manufactureing, test data of the characteristics as an overpack and so on. The basic structure of the database has already been completed last year. At present, two main data; corrosion data and the test data of overpack welding and inspections, are being summarized and imported into the database system. In this report, contents of the table were discussed and the datasets that have already been imported into the database system were appended.