Abstract
In connection with the development of vitrified solidification processes of high-level liquid wastes at Power Reactor and Nuclear Fuel Development Corp. (PNC), the characterization of the various borosilicate glasses containing the simulated high-level radioactive wastes have been carried out at Government Industrial Research Institute, Osaka.The volatility, the viscosity and the electrical conductivity of glasses in molten states have been measured, and the thermal conductivity, the elastic modulus, the chemical durability and the crystallization behavior in solid states have been also investigated. These data seem to be useful in the construction and operation of the engineering scale faci1ity at PNC.The low-melting temperature glasses have large volatilization rates, low viscosities in molten states, low crystallization temperatures and less durabilities with water in solid states. Therefore, the high-melting temperature glasses seem to be suitable for storage of wastes from the view point of safety evaluation, although in this case it is necessary to improve the melting technique to avoid violent evaporation.
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