用于固定放射性液体废物的多组分硼硅玻璃微珠的合成与特性分析

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2024-10-28 DOI:10.1016/j.jnucmat.2024.155485

Sitendu Mandal , Gattu Suneel , Jayaprakasam Selvakumar , Kaushik Biswas , Srikrishna Manna , Sourav Nag , Balram Ambade

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引用次数: 0

摘要

高放射性液体废物（HLW）通过一种称为玻璃化的工艺固定在玻璃基质中。在这一过程中，高放射性废物和玻璃形成氧化物在玻璃熔炉中以预先确定的比例结合，产生玻璃化废物形式。这种废物形式的特性，包括其容纳不同放射性同位素的能力，取决于基础玻璃的成分。在本研究中，开发了珠状（直径 2-3 毫米）的多组分无定形硼硅酸盐玻璃（SiO2-B2O3-Na2O-TiO2-Fe2O3-CaO-K2O）。使用光学发射光谱仪分析了玻璃珠（GBs）的元素组成。此外，还对玻璃珠进行了各种物理化学分析，包括官能团鉴定、热学、电学和机械性能，以及粘度和化学耐久性评估，以确定最佳玻璃成分。此外，还研究了 Na2O 对浇注温度的影响。此外，还进行了压碎强度和损耗率测量，以确认国标玻璃是否适合远程送入熔化炉。这项研究中开发的国标玻璃是独一无二的，具有在全球玻璃化设施中使用的巨大潜力，特别是在采用焦耳加热陶瓷熔化器（JHCM）技术的连续玻璃化系统中。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

Synthesis and characterization of multi-component borosilicate glass beads for radioactive liquid waste immobilisation

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Synthesis and characterization of multi-component borosilicate glass beads for radioactive liquid waste immobilisation

High-level radioactive liquid waste (HLW) is immobilized in a glass matrix through a process called vitrification. In this process, HLW and glass-forming oxides are combined in a pre-determined ratio within a glass melter to produce a vitrified waste form. The properties of this waste form, including its ability to accommodate different radioactive isotopes, depend on the composition of the base glass.

In the present study, multi-component amorphous borosilicate-based glasses (SiO₂-B₂O₃-Na₂O-TiO₂-Fe₂O₃-CaO-K₂O) in bead form (diameter 2–3 mm) were developed. The elemental composition of the glass beads (GBs) was analyzed using an optical emission spectrometer. Additionally, the GBs underwent various physico-chemical analyses, including functional group identification, thermal, electrical, and mechanical properties, as well as viscosity and chemical durability assessments, to identify the optimal glass compositions. The influence of Na₂O on the pouring temperature was also examined. Crushing strength and attrition rate measurements were conducted to confirm the suitability of GBs for remote feeding into the melter. The GBs developed in the study are unique, with significant potential for worldwide use in vitrification facilities, particularly in continuous vitrification systems employing Joule Heated Ceramic Melter (JHCM) technology.

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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.