The investigation consists of three parts and shall provide an input to the – empirical – PTA-2 study to be undertaken by SCK•CEN (called “lens”):<br>A. Compilation of – selected – existing PTA methods and procedures identifying requisites, practices, benefits, and challenges to answer the key questions in the context of WP1 about a PTA “toolbox”: “What can you apply, when can you apply, and what is needed to apply?” The multi-dimensional context of a possible “PTA situation” is analysed; suitable and nonsuitable methods, techniques and procedures are discussed.<br>B.

The preceding RD&D-Programme from 2001 was concentrated on research and technology development. Research with a focus on the assessment of long-term safety was emphasized and viewpoints from previous reviews of SR 97 and RD&D-Programme 98 were dealt with in depth. SR 97 was an assessment of the long-term safety of a deep repository for spent nuclear fuel. This RD&D-Programme 2004 focuses its attention on the development of technologies for fabrication and sealing of canisters for final disposal of spent fuel.

The primary objective of government policy, and of NUMO in implementing this policy is to ensure that a repository for Japan’s high-level radioactive waste is designed and located so as to provide secure isolation of the waste and adequate safety for present and future generations. This requires that the site of a repository has to be chosen carefully and an associated repository concept is selected which is appropriate for its specific geological and environmental conditions. At NUMO, we have chosen to implement a volunteering approach to siting.