Development Of Glass-Melting Technology For Nuclear Waste Vitrification (In Japanese)

Test process of Power Reactor and Nuclear Fuel Development Corp of Japan was described. Standard deviation limits of the components in solidified glasses were given. Changes in leaching rate by H2O and high-temperature viscosity of the glasses with composition were given. The additive glass was fed in the form of sintered fibre, and the waste was fed in the form of solutions. The mixtures were heated by direct Joule's heating to form glass melts. The furnace was composted of chromite-type refractories and Ni-Cr alloy electrodes. The furnace structure is shown.