Investigation of the insulating properties of the Cherkasy deposit clays for the creation of underlying screens of radioactive waste at the ‘Vector’ site

B. Shabalin, O. Lavrynenko, K. Yaroshenko
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Abstract

The lack of scientifically substantiated requirements, comprehensively developed and approved in a prescribed manner, for the usage of clays as a barrier material poses risks for the safe disposal of radioactive waste in facilities at the ‘Vector’ site for the period of their operation and closure. The bentonite clay from Ukraine’s largest Cherkasy deposit of bentonite and palygorskite clays is considered the most durable as the main component of the insulating (underlying) screens of radioactive waste disposal facilities. The main properties and compositional features of the Cherkasy natural bentonite clay (Dashukovskaya site, layer II) and its variety such as alkaline earth bentonite (activated soda bentonite), which provide isolation of radioactive waste in disposal, are considered. It is shown that the Cherkasy field has good waterproofing and barrier properties, including a high sorption capacity with respect to 90Sr and 137Cs, which is one of the main characteristics that ensure the safe disposal of radioactive waste. The alkaline earth bentonite absorbs 90Sr and 137Cs more efficiently than natural bentonite does. However, 90Sr is sorbed in larger quantities than 137Cs on both types of bentonite. With increasing time of interaction with an aqueous solution, both types demonstrate a redistribution of the mobile (exchangeable) and immobile (non-replaceable) forms of radionuclides. The contribution of the stationary form that does not participate in migration processes also increases. A comprehensive analysis of the bentonite clays of the Cherkasy deposit was carried out, taking into account the significance of recoverable reserves and the potential for improving the technical and economic parameters of clays. Thus, the Cherkasy bentonite clays can be recommended as an additional anti-migration engineering barrier for ground/near-surface facilities for the disposal of radioactive waste. When choosing the type of bentonite clay for use as a barrier in a radioactive waste disposal facility, one could take into account the data published in the article, but the question of applying the bentonite clays of the Cherkasy deposit to ensure the safe disposal of radioactive waste remains to be  further studied.
研究切尔卡西沉积粘土的绝缘性能,用于在“矢量”场址创建放射性废物的底层屏障
在使用粘土作为屏障材料方面,缺乏科学依据、全面制定和以规定方式批准的要求,这给“矢量”场址设施在运行和关闭期间的放射性废物安全处置带来了风险。来自乌克兰最大的切尔卡西(Cherkasy)膨润土和斜长石粘土矿床的膨润土粘土被认为是最耐用的,是放射性废物处理设施绝缘(底层)屏障的主要组成部分。介绍了切尔卡西天然膨润土粘土(达舒科夫斯卡亚遗址第二层)及其碱土膨润土(活性苏打膨润土)等在处置中对放射性废物起到隔离作用的主要性质和组成特征。结果表明,切尔卡西油田具有良好的防水阻隔性能,对90Sr和137Cs具有较高的吸附能力,这是保证放射性废物安全处置的主要特征之一。碱性土膨润土对90Sr和137Cs的吸附效果优于天然膨润土。然而,90Sr在两种膨润土上的吸附量都大于137Cs。随着与水溶液相互作用时间的增加,两种类型的放射性核素都表现出可移动(可交换)和不可移动(不可替换)形式的重新分配。不参与迁移过程的固定形式的贡献也在增加。考虑到可采储量的重要性和改善粘土技术经济参数的潜力,对切尔卡西矿床的膨润土粘土进行了全面分析。因此,切尔卡西膨润土粘土可以推荐作为地面/近地面设施处理放射性废物的额外防迁移工程屏障。在选择用作放射性废物处置设施屏障的膨润土类型时,可以考虑文章中公布的数据,但应用切尔卡西矿床的膨润土粘土来确保放射性废物的安全处置的问题仍有待进一步研究。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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