Development of a source term for radionuclide release from spent fuel in a basalt repository

An analysis of groundwater transport of radionuclides from a nuclear waste repository requires a source term, i.e., a prediction of the rate of release of radionuclides from the repository. A source term has been constructed to support a demonstration of analytical methodology developed for use in repository licensing. For this the case of release from spent fuel in a basalt repository sheared by a fault was considered. The resulting source term illustrates the role of leaching behavior without referring to a specific detailed waste package design. The technical approach used to construct the source term is discussed to illustrate how information on nuclear waste leaching behavior might be used in support of repository licensing activites. Assumptions made in lieu of a complete understanding of leaching behavior are discussed