Safety of nuclear waste repositories

Abstract

A short overview is given of different nuclear waste repository concepts, followed by a more detailed discussion of Swiss radioactive waste management planning. Waste types and characteristics and the concept for their disposal are summarised. The safety concept involving a multi-barrier system is illustrated with the example of vitrified high-level waste. Important geochemical parameters and processes for repository safety are listed, and some selected aspects concerning porewater chemistry, solubility limits and sorption of radionuclides are discussed in detail with specific examples. © Schweizerische Chemische Gesellschaft.