Leaching of B-Si-glass by water in the presence of bentonite

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-09-04 DOI:10.1016/j.jnucmat.2025.156133

Victor Malkovsky, Sergey Yudintsev, Maximilian Niсkolsky

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Abstract

Incorporation of high-level radioactive waste (HLW) into borosilicate glass is used on an industrial scale in most countries developed large-scale nuclear power engineering with closed fuel cycle. The vitrified HLW in a steel canister is planned to be disposed of in an underground repository. The bentonite clay serves as an important protective barrier and can significantly influence the durability of the borosilicate glass when groundwater penetrates the canister due to corrosion of its walls or mechanical damage resulting from rock movement caused by rock bursts or increased seismic activity. An experimental study of the leaching of borosilicate glass with simulators of HLW components (U, REEs, corrosion products) by water in the presence of bentonite has been carried out. The effect of the initial mass ratio of water to bentonite on the leaching rate of the glass is analyzed. Colloidal forms of glass leaching products are revealed by filtering the leach solution through membranes of different pore sizes. The elemental content of the filtrates was determined by inductively coupled plasma mass spectroscopy (ICP MS). The surface and cross section of the glass after leaching were studied using scanning electron microscopy (SEM) combined with energy dispersive X-ray analysis (EDX). The influence of the mass ratio of water and bentonite on the leaching of borosilicate glass can be noticeable at the beginning of the process. The presence of bentonite affects the colloidal form of radionuclide simulants in the leach products, in particular, the uranium-bearing colloid in the leach solution decreases radically. The outer surface of the altered glass layer is significantly enriched with aluminum in the presence of bentonite.

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膨润土存在下b -硅玻璃的水浸出

将高放射性废物（HLW）掺入硼硅酸盐玻璃中已在大多数发达的闭式燃料循环大型核电工程中得到工业规模的应用。玻璃化的高烈性武器装在钢罐中，计划在地下储存库中处置。膨润土粘土是一种重要的保护屏障，当地下水由于岩爆或地震活动增加引起的岩石运动引起的壁腐蚀或机械损伤而渗入罐体时，膨润土粘土可以显著影响硼硅酸盐玻璃的耐久性。在膨润土存在的情况下，用高分子量组分（U、ree、腐蚀产物）模拟器对硼硅酸盐玻璃进行了浸出实验研究。分析了水与膨润土的初始质量比对玻璃浸出率的影响。通过不同孔径的膜过滤浸出液，揭示了玻璃浸出产物的胶体形态。滤液的元素含量采用电感耦合等离子体质谱法（ICP MS）测定。利用扫描电子显微镜（SEM）和能量色散x射线分析（EDX）对浸出后玻璃的表面和截面进行了研究。水与膨润土的质量比对硼硅玻璃浸出的影响在工艺开始时是明显的。膨润土的存在影响了浸出产物中放射性核素模拟物的胶体形态，特别是浸出溶液中的含铀胶体从根本上减少。在膨润土存在的情况下，蚀变玻璃层的外表面显著富集铝。

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.