[en] In contrast to normal practice of employing theoretical considerations, a scheme based on practical approach has been evolved for the development of suitable glass compositions to produce vitrified radioactive wastes with low forming temperatures of around 1000degC and low leach rates of the order of 10^-5 to 10^-6 gm cm^-2 d^-1. After fixing the percentage of the waste content at a moderate value, a number of formulations in the sodium borosilicate system are studied for their melting and leaching characteristics by simple and quick laboratory techniques. Based on the results, a composition with scope for further lowering of melting temperature and improvement in product durability is subjected to the introduction of different durability enhancing and/or melting temperature lowering oxides as well as the waste oxides so as to obtain an optimum composition. This composition is further subjected to variations in its Na₂O, Ba₂O₃ and SiO₂ content to get a region of compositions with optimum leaching and melting characteristics. A composition selected from the central portion of this region will retain its properties even if the proportion of waste oxides and glass forming additives vary during the commercial production of vitrified radioactive wastes. (auth.)