4.7 Article

Uranium immobilization by FEBEX bentonite and steel barriers in hydrothermal conditions

期刊

CHEMICAL ENGINEERING JOURNAL
卷 269, 期 -, 页码 279-287

出版社

ELSEVIER SCIENCE SA
DOI: 10.1016/j.cej.2015.01.134

关键词

Bentonite; Smectite; Disilicates; Steel; Uranium; Radioactive waste

资金

  1. ENRESA [0079000121]
  2. Junta de Andalucia and FEDER funds [P12-FQM-567]

向作者/读者索取更多资源

FEBEX clay is considered a reference material in engineered barriers for safe storage of nuclear waste and uranium is a minor component of high-level radioactive waste (HLRW) and a main component of the spent nuclear fuel (SNF). Here, the kinetics of reaction of uranium with FEBEX was investigated in addition to the uranium immobilisation ability and the structural analysis of the reaction products. Hydrothermal treatments were accomplished with UO22+ and tetravalent actinide simulator ZrO2+, also present in HLRW. The quantification of the reaction was performed through gamma spectrometry of uranium. Two mechanisms for UO22+ retention by FEBEX were detected: adsorption and formation of stable and insoluble new phases. The structural analyses performed using ZrO2+, confirmed the uranium adsorption and the presence of new phases, ZrO2 and Zr(SiO4), that emphasise the existence of a chemical reaction with the bentonite. The analysis of the velocity of reaction uranium-clay minerals revealed temperature dependence. An exponential fitting suggested that the removal of uranium from solution at temperatures over 200 degrees C could be completed in less than a year. For lower temperatures, several years are needed. Milliequivalents of UO22+ immobilised by the clay depended on temperature and time and were over cation exchange capacity (CEC) of FEBEX even at 100 degrees C (reaching 600% of CEC). The reaction with steel, also temperature dependent, was finally analysed. At 200 degrees C 40-70% of uranium reacted with steel. But only 30-15% reacted at 300 degrees C and 100 degrees C. The reactions provide a stable immobilisation mechanism for uranium even when its sorption and swelling capacities fail. Our experiments will be of particular interest for very deep borehole disposals were higher temperatures and pressures are expected. (C) 2015 Elsevier B.V. All rights reserved.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.7
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

暂无数据
暂无数据