Estimation of tritium transfer parameters in biphasic lithium ceramic based on the results of reactor irradiation experiments

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

Fusion Engineering and Design Pub Date : 2025-06-20 DOI:10.1016/j.fusengdes.2025.115282

Timur Kulsartov , Zhanna Zaurbekova , Regina Knitter , Julia Leys , Asset Shaimerdenov , Yevgen Chikhray , Saulet Askerbekov , Inesh Kenzhina , Alexandr Yelishenkov

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引用次数: 0

Abstract

It is expected that the development of thermonuclear fusion will be able to easily satisfy the energy needs of humanity. There are enough fuel reserves for the fusion reaction: tritium can be bred via a ⁶Li(n,α)³H reaction from lithium, which is common in nature, and deuterium is quite easily extracted from seawater. One of the problems on the way to implement thermonuclear fusion today is the search for and development of breeder materials that can withstand the high radiation and energy loads that are expected in a long-pulsed fusion devices.

Various types of lithium-containing ceramic materials are currently being actively studied for use as a breeder material in helium-cooled breeder blanket concepts.

This study focuses on the methodology and results of calculations of tritium residence time in the samples of biphasic lithium ceramic pebble bed containing nominal 65 mol % lithium orthosilicate and 35 mol % lithium metatitanate (pebble diameter 0.25 -1.250 mm).

The values of the tritium residence time obtained as a result of modeling the release of tritium from ceramics within the framework of the diffusion-desorption model have a temperature dependence of lgτ = -1.374+1676/t. They are in good agreement with the literature data, suggesting that the tritium residence time increases with increasing open porosity.

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基于反应堆辐照实验结果的双相锂陶瓷中氚转移参数估算

人们期望热核聚变的发展能够轻松地满足人类的能源需求。有足够的燃料储备用于聚变反应：氚可以通过锂的6Li(n,α)3H反应繁殖，这在自然界中很常见，氘很容易从海水中提取。当今实现热核聚变的问题之一是寻找和发展增殖材料，这些材料能够承受长脉冲聚变装置中预期的高辐射和能量负荷。目前正在积极研究各种类型的含锂陶瓷材料作为氦冷却增殖毯概念中的增殖材料。本文主要研究了含65 mol %正硅酸锂和35 mol %偏钛酸锂的双相锂陶瓷球床样品（球直径0.25 -1.250 mm）中氚停留时间的计算方法和结果。在扩散-解吸模型框架内对陶瓷中氚的释放进行建模所得到的氚停留时间值具有温度依赖性，其值为lgτ = -1.374+1676/t。这与文献数据吻合较好，表明氚的停留时间随孔隙度的增加而增加。

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.