Durability of vitrified highly active waste from nuclear reprocessing

摘要: THE future of nuclear power is often said to depend on the development a satisfactory method for dealing with highly radioactive waste such as liquid which produced during extraction plutonium from irradiated fuel. (See recommendation 27 in ref. 1). Much attention now being given developing processes suitable solidifying active waste2 and conversion borosilicate glass seems most favourable route. Here we report recent investigation at Harwell supports belief that installation full-scale vitrification process will be successfully achieved.