An assessment of overseas developments in methods for treatment and disposal of high-level radioactive wastes

Abstract

The principles of management and disposal of highly radioactive wastes contained in spent fuel from nuclear power generation are described. The status of developments in spent fuel reprocessing high-level waste solidificaton and geologic isolation is reviewed. Some generic studies on the possible range of annual radiological doses to individuals from waste repositories are discussed and compared with doses from some existing nuclear power and fuel cycle operations and with the dose received annually from an average background of naturally occurring radiation.