利用鼓泡系统测量聚变中子辐照下 Li2TiO3 增殖器的氚释放量

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Wenhao Wu , Haixia Wang , Xuewei Fu , Jiaqing Wang , Chao Chen , Taosheng Li
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引用次数: 0

摘要

在氘-氚(D-T)聚变反应堆的固体增殖器中,氚的增殖源于锂原子与中子的反应。由于 D-T 核聚变反应堆尚未建成,加速器型核聚变中子源可用于氚生产实验。目前观测到的氚产量水平有限。在测量低浓度氚时,常用的方法是收集从增殖器中由气泡释放出来的氚,然后用液体闪烁计数器(LSC)进行测量。因此,要想有效地收集氚,并准确地得出氚释放行为的结果,选择鼓泡器至关重要。为了最大限度地收集氚,本研究首先利用标准氚水(HTO)调查了鼓泡器中不同液体容量的性能,随后通过加速器型聚变中子源辐照 Li2TiO3 增殖器的氚释放实验验证了这些选择。结果表明,总容积为 60 毫升、装满 20 毫升液体的鼓泡器具有出色的氚收集效率和可重复性,饱和系数接近 1。中子模拟结果进一步证实,所选鼓泡系统的收集效率接近 100%。模拟的氚释放总量与鼓泡系统和 LSC 的测量值一致。这些发现为聚变中子辐照固体增殖器的氚释放行为研究提供了技术支持。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Measurement of tritium release from Li2TiO3 breeder under fusion neutron irradiation by bubbling system

In the solid breeder of deuterium-tritium (D-T) fusion reactor, tritium breeding stems from the reaction between Li atoms and neutrons. Due to the D-T fusion reactor has not been built yet, the accelerator-type fusion neutron source could be applied to tritium production experiments. The tritium yield is currently observed to be at a limited level. For measuring low-concentration tritium, the common method is to collect the tritium released from the breeder by the bubblers and then measure it with the liquid scintillator counter (LSC). Therefore, the selection of bubblers is crucial for effective tritium collection and accurate results of tritium release behavior. To maximize tritium collection, this study initially investigated the performance of different liquid volumes in bubblers utilizing standard tritiated water (HTO) and subsequently validated these selections through experiments involving tritium release of Li2TiO3 breeders irradiated by the accelerator-type fusion neutron source. The results demonstrated that the bubbler of total volume 60 ml filled with 20 ml liquid exhibited excellent tritium collection efficiency and repeatability, with the saturation coefficient close to 1. The selected bubbling system with catalytic oxidation was used to identify the different forms of tritium release from the tritium breeder irradiated by fusion neutrons. Neutronic simulation results further confirmed that the selected bubbling system had nearly 100 % collection efficiency. The simulated total amount of tritium released was consistent with the measured value of the bubbling system and LSC. These findings provide technical support for the study on the tritium release behavior of solid breeders irradiated by fusion neutrons.

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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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