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首页> 美国政府科技报告 >Preparation and Characterization of an Improved Borosilicate Glass for the Solidification of High Level Radioactive Fission Product Solutions (HLW). Pt. 2
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Preparation and Characterization of an Improved Borosilicate Glass for the Solidification of High Level Radioactive Fission Product Solutions (HLW). Pt. 2

机译：用于高放射性裂变产物溶液（HLW）固化的改进硼硅酸盐玻璃的制备和表征。铂。 2

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In the 'Institut fuer Nuklare Entsorgungstechnik' the borosilicate glass VG 98/12 has been developed for the solidification of the high level radioactive waste (HLW). This borosilicate glass can be used in a direct heated ceramic melter and forms together with the HLW the borosilicate glass product GP 98/12. This borosilicate glass product has been examined in detail both in liquid and solid state. The elements contained in the HLW can be incorporated without problems. Only in a few exceptions the concentration must be kept below certain limits to exclude the formation of a second phase ('yellow phase') by separation. No spontaneous crystallization and no crystallization over a long time could be observed as long as the temperature of the borosilicate glass product is kept below its transformation area. Simulating accidental conditions in the final storage, samples had been leached at temperatures up to 200 exp 0 C and pressures up to 130 bar with saturated rock salt brine and saturated quinary salt brine. The leaching process seems to be stopped by the formed 'leached layer' on the surface of the borosilicate glass product after a limited leaching time. Detailed investigations have been started to explain this phenomenon. (ERA citation 08:007007)

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