Advanced Vitreous Wasteforms for Radioactive Salt Cake Waste Immobilisation

Авторы: Kashcheev V.A., Musatov N.D., Ojovan M.I.
Журнал: MRS Advances
Том: 5
Номер: 3-4
Год издания: 2020
Первая страница: 121
Последняя страница: 129
DOI: 10.1557/adv.2020.45
Аннотация: Salt cake radioactive waste is a remnant solid salt concentrate after deepevaporation of radioactive evaporator concentrate at WWER NPP’s. The traditionalcementing of borate-containing liquid radioactive waste, to which the salt cake belongs, leadsto a significant increase in the volume of the final product. This work describes borosilicatevitreous wasteforms developed to immobilize radioactive salt cake waste and comprises dataon both glass synthesis and characterization. The composition of glass selected for thepurpose of immobilisation of the salt cake radioactive waste allows to include up to 40 wt. %of the oxides contained in the salt cake and to reduce the volume of the final product by morethan 2 times compared with the cement compound. The batches were melted in a cold cruciblemelter at 1200 ℃. The normalized cesium leaching rate of the vitrified wasteform product waswithin range 3.0·10-5 – 3.7·10-6 g/(cm2·day).
Добавил в систему: Ожован Михаил Иванович

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