Gas release kinetics from neutron irradiated Li2TiO3 samples

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-12 DOI:10.1016/j.fusengdes.2025.115060

Saulet Askerbekov , Magzhan Aitkulov , Asset Shaimerdenov , Timur Kulsartov , Assyl Akhanov , Zhanar Bugybay , Darkhan Sairanbayev

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引用次数: 0

Abstract

This study investigates the kinetics of residual tritium release from neutron-irradiated samples of Li-6 enriched lithium metatitanate (Li₂TiO₃) using the thermal desorption spectroscopy (TDS) method. The samples were subjected to low-temperature neutron irradiation in the peripheral channel of the WWR-K reactor (Almaty, Kazakhstan) for 21 days. The accumulated thermal neutron fluence was 3.0 × 10^–19 см^-2. During the experiments, the samples were linearly heated from room temperature to 1173 K at different heating rates. The released gaseous products were recorded using an RGA-100 mass spectrometer under deep vacuum conditions.

The experimental results revealed two distinct peaks of tritium release, corresponding to different retention mechanisms:

•
The first peak (630–707 K) has a low activation energy (56 kJ/mol) and a small pre-exponential factor (7 c^-1), indicating desorption of tritium from the surface and from the open porosity.
•
The second peak (713–794 K) is characterized by a higher activation energy (74 kJ/mol) and an increased pre-exponential factor (31 c^-1), indicating the release of tritium from the closed porosity and near-surface layers.

It was established that tritium is predominantly released in the form of HT. Thus, the obtained data enable both qualitative and quantitative characterization of the kinetic parameters of tritium release from Li₂TiO, which can be useful for the selection and optimization of breeder materials for fusion reactors.

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中子辐照Li2TiO3样品气体释放动力学

采用热解吸光谱（TDS）方法研究了富集Li-6的偏钛酸锂（Li2TiO3）中子辐照样品中残余氚的释放动力学。样品在WWR-K反应堆（哈萨克斯坦阿拉木图）外围通道进行低温中子辐照21天。累积热中子通量为3.0 × 10-19 см-2。实验过程中，以不同的升温速率将样品从室温线性加热至1173 K。在深真空条件下，用RGA-100质谱仪记录了释放的气态产物。•第一个峰（630-707 K）具有较低的活化能（56 kJ/mol）和较小的指前因子（7 c-1），表明氚从表面和开放孔隙中解吸。•第二个峰（713-794 K）具有较高的活化能（74 kJ/mol）和增加的指数前因子（31 c-1），表明氚从封闭孔隙和近表层释放。已经确定氚主要以HT的形式释放。因此，所获得的数据可以定性和定量表征Li2TiO释放氚的动力学参数，这可以用于聚变反应堆增殖材料的选择和优化。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.