Processing of radioactive wastes from long-term fuel store of A-1 nuclear power plant

A solidification system was designed for the very special composition of radioactive wastes of non-standard type generated in the A-1 nuclear power plant. The system was tested on laboratory scale and tests under pilot plant conditions have just started. The chemical composition of the intermediate-level wastes is not accurately known but in the routine fuel cycle of nuclear power plants it certainly does not occur. The designed system is based on vitrification, attention mainly being centred on the development of suitable glasses. A detailed presentation is made of the results of the development of lead glasses and glasses with a high titanium content. Tests were made with radioactive samples of wastes and with selected types of glass. An experimental melting facility was built which allows to process a model, i.e., non-radioactive, waste of the A-1 type to a scale of 1:1. Pilot plant experiments on the facility will be followed by the design and construction of a fully operational facility. (Z.M.)