{"title":"Tritium release behavior and application of a release model for the neutron-irradiated biphasic lithium ceramics","authors":"Yuguo Zhang , Qilai Zhou , Anjie Yang , Asahi Sanfukuji , Yasuhisa Oya","doi":"10.1016/j.fusengdes.2024.114593","DOIUrl":null,"url":null,"abstract":"<div><p>In this study, neutron irradiation for the Li<sub>2</sub>TiO<sub>3</sub>-Li<sub>4</sub>SiO<sub>4</sub> 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 Li<sub>2</sub>TiO<sub>3</sub> and Li<sub>4</sub>SiO<sub>4</sub> 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.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379624004459","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
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.
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.