用 Na2O-B2O3-SiO2 基质固定 TRPO 废物：含钕晶体的影响

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

Journal of Nuclear Materials Pub Date : 2024-11-17 DOI:10.1016/j.jnucmat.2024.155528

Yang Li , Fen Luo , Jiahong Wang , Yu Gao , Gangchuan Ji , Xirui Lu

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引用次数: 0

摘要

本研究使用 Na2O-B2O3-SiO2 三元基质来模拟复杂 TRPO 废物的固定化。研究调查了不同 TRPO 废物含量的固化体与其固溶性、傅立叶变换红外光谱、维氏硬度和密度之间的关系。研究发现，Na2O-B2O3-SiO2 基体可固定的最大 TRPO 废物量为 20 wt.%。当 TRPO 废料含量在 5-15 重量%之间时，其主要固定在玻璃相中。当 TRPO 废料含量超过 20 wt.% 时，出现了含有主要废料元素钕的结晶相 NdBO3 和 Na3Nd(BO3)2。含有 20 重量%TRPO 废料的样品的沥滤量为 10-6 g-m-2-d-1。NdBO3 和 Na3Nd(BO3)2 晶体的存在导致样品的维氏硬度和密度下降。维氏硬度和密度的最高值分别为 6.77 GPa 和 2.7 g-1cm-3。本研究中使用的硼硅酸盐基质已被证明可有效固定复杂的 TRPO 废物，并有望成为 TRPO 废物的处理基质。

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Immobilization of TRPO waste by Na2O-B2O3-SiO2 matrix: Effects of Nd-containing crystals

This study used a ternary Na₂O-B₂O₃-SiO₂ matrix to simulate the immobilization of complex TRPO waste. The study investigated the relationship between the solidified bodies with different TRPO waste contents and their solid solubility, FT-IR, Vickers hardness, and density. The study found that the maximum amount of TRPO waste that can be immobilized in the Na₂O-B₂O₃-SiO₂ matrix was 20 wt.%. When the TRPO waste content ranged from 5-15 wt.%, it was primarily immobilized in the glassy phase. When the TRPO waste content exceeded 20 wt.%, the crystalline phases NdBO₃ and Na₃Nd(BO₃)₂, which contain the main waste element Nd appeared. Samples containing 20 wt.% TRPO waste resulted in leaching of 10^-6 g·m^-2·d^-1. The presence of NdBO₃ and Na₃Nd(BO₃)₂ crystals resulted in a decrease in the Vickers hardness and density of the samples. The highest values for Vickers hardness and density were 6.77 GPa and 2.7 g^-1cm^-3, respectively. The borosilicate matrix utilized in this study has proven to be an effective immobilization of complex TRPO wastes and holds promise as a treatment matrix for TRPO wastes.

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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.