中子辐照双相锂陶瓷的氚释放行为和释放模型的应用

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-19 DOI:10.1016/j.fusengdes.2024.114593
Yuguo Zhang , Qilai Zhou , Anjie Yang , Asahi Sanfukuji , Yasuhisa Oya
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引用次数: 0

摘要

本研究在京都大学研究堆(KUR)对 Li2TiO3-Li4SiO4 双相陶瓷进行了中子辐照。氚热解吸光谱(tritium-TDS)和电子自旋共振(ESR)是在静冈大学的辐射控制区进行的。结果表明,氚解吸的特殊性与陶瓷中 Li2TiO3 和 Li4SiO4 的相位比以及中子通量有关。基于扩散和脱氚动力学,对双相陶瓷中的氚迁移过程进行了深入研究。考虑到辐照缺陷对氚的捕获以及从体表到体表的扩散/迁移过程,建立了氚释放模型。所提出的模拟代码可以很好地再现实验数据。模拟过程得到的动力学参数与实验结果基本一致。此外,还研究了晶粒尺寸和相比对氚释放特性的影响。该模拟代码也可应用于颗粒或鹅卵石。此外,该模拟代码还适用于了解聚变反应堆工作状态下的氚释放行为。结果发现,当毯子在较高温度下运行时,氚的释放可以达到稳定状态。反应堆关闭后,陶瓷中的氚保留得到了证实。通过控制毯式系统的温度,可以减少氚的存量。
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Tritium release behavior and application of a release model for the neutron-irradiated biphasic lithium ceramics

In this study, neutron irradiation for the Li2TiO3-Li4SiO4 biphasic ceramics was conducted at Kyoto University Research Reactor (KUR). The tritium thermal desorption spectroscopy (tritium-TDS) and the electron spin resonance (ESR) were performed in the radiation-controlled area at Shizuoka University. It was confirmed that the tritium desorption peculiarities were dependent on the phase ratio of Li2TiO3 and Li4SiO4 in the ceramic and the neutron fluence. The tritium migration process in biphasic ceramics was intensively studied based on the diffusion and de-trapping kinetics. A tritium release model was established with the consideration of the tritium trapping by irradiation defects and diffusion/migration process from bulk to surface. The experimental data can be well reproduced by the proposed simulation code. The kinetic parameters obtained by the simulating process were almost consistent with the experimental results. The effects of grain size and phase ratio on the tritium release characteristics were also investigated. The simulation code can be also applied to pellets or pebbles. Besides, the simulation code was adapted to understand the tritium release behavior in the working condition of fusion reactors. It was found that the tritium release could reach a steady state when the blanket was operated at higher temperatures. The tritium retention in ceramics after the shutdown of the reactor was confirmed. The tritium inventory can be reduced by controlling the temperature of the blanket system.

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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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