1. Scope

Keywords

Rationale

In comparison with spent fuels from pressurized water reactors, spent fuels from fast breeder reactors contain much more transuranic elements and fission products, and hence are of much higher radioactivity. This makes the traditional wet reprocessing method by solvent extraction difficult and as a result the pyro-reprocessing method by molten salts was developed. In this case, high level waste salts will be produced instead of high level liquid waste. In order to protect human beings and the environment from the danger caused by the highly water-soluble salts, proper solidification measures must be taken prior to the final geological disposal.