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AbstractAbstract
[en] The transformation into a vitrified block of highly radioactive liquid wastes is actually the best solution for the storage in long run. In West Germany, the research institute in the field of nuclear energy (KfK) has been oriented in this way by developing industrial processes of vitrification and by following studies on the behaviour of the final products. For the fission products, the chosen glasses present good stability characteristics and are used as a first barrier during confinement. Our work, which is part of the research program on radioactive waste vitrification, consists of preparing borosilicate glass GP 98/12 and studying physical and chemical characteristics. We have also contributed to the development and the realization of glass blocks sampling system prepared at pilot scale
Original Title
Elaboration et etude du verre borosilicate GP 98/12 pour la vitrification des dechets radioactifs du Centre de KfKarlsruhe (R.F.A.)
Primary Subject
Secondary Subject
Source
Sep 1987; 133 p; Theses (Magister).
Record Type
Report
Literature Type
Thesis/Dissertation
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