Adsorption of cesium and strontium on natrified bentonites

被引:43
|
作者
Galambos, Michal [1 ]
Kufcakova, Jana [1 ]
Rosskopfova, Ol'ga [1 ]
Rajec, Pavol [1 ]
机构
[1] Comenius Univ, Dept Nucl Chem, Fac Nat Sci, Bratislava 84215, Slovakia
关键词
Chemical modification; Natrification; Activation; Slovak Na-bentonite; Smectite; Montmorillonite; Adsorption; Cesium; Strontium; Deep geological repository; COLLOIDAL PROPERTIES; ORGANIC-COMPOUNDS; STRUCTURAL-PROPERTIES; LIESKOVEC DEPOSIT; MONTMORILLONITE; CLAY; SORPTION; DISPERSIONS; STABILITY; BEHAVIOR;
D O I
10.1007/s10967-009-0424-9
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
The influence of chemical activation-natrification of bentonites on adsorption of Cs and Sr was studied with regards to utilization of bentonites for depositing high-level radioactive waste and spent nuclear fuel. Bentonite samples from three Slovak deposits in three different grain-size (15, 45 and 250 mu m), natural and natrified forms (Na-bentonites); under various experimental conditions, such as contact time, adsorbent and adsorbate concentration have been studied. When comparing the Na-bentonites and their natural analogues, the highest adsorbed Cs and Sr amounts were reached on the natrified samples. After the Sr adsorption a drop in the pH equilibrium value was observed together with the increase of the initial Sr concentration. A disadvantage of the natrified bentonite forms is formation of colloid particles. After 2 h of phase mixing a gentle turbidity was observed as well as formation of a gel-like form. The above findings were confirmed by observing the particle distribution in dry and wet dispersion and centrifugation at two different speeds. Natrification as a technological process of bentonite quality improvement cannot be applied when constructing a long-term repository for high-level radioactive waste and spent nuclear fuel. The main problem of natrification is a technological process which leads to a significant pH increase. Alkaline environment in combination with the K presence and increased temperature in the vicinity of radio-active waste can lead to a rapid illitization of smectite and loss of the original adsorption qualities. Moreover, sodium additions are a significant point of uncertainty since it is not possible to state what amount of Na enters the interlayer space and what amount stays in the inter-partition space.
引用
收藏
页码:803 / 813
页数:11
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