Xiaoyue Hu , Qingsheng Hu , Jiahong Li , Chuansen Yang , Junru Chen , Changjun Xu , Haiyang Xu , Juan Jiang , Junyu Zhao
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引用次数: 0
Abstract
There are approximately 33,000 blocks of boron carbide (B4C) employed as the main neutron shielding material in the International Thermonuclear Experimental Reactor (ITER) Equatorial Port#12 Integration System (EQ#12) in-vessel components. The gases desorbed from the surface and diffused from B4C internally can adversely affect the vacuum environment of ITER device. Therefore, it is crucial to study its vacuum outgassing characteristics for ensuring the vacuum performance of the ITER device. In this paper, B4C block with an average density of (2.50±0.01) g/cm³ were prepared via the hot-pressing process. Utilizing a self-developed outgassing rate testing equipment, the outgassing characteristics of two kinds of B4C samples (non-prebaked and prebaked at 900 °C) were studied by switching between two pumping paths method. Results indicate that after the ITER thermal cycle, the outgassing rate per unit area of all B4C samples were as low as the order of 10–9 Pa·m3·s−1·m-2, the H2O content is significantly decreased, with H2 constituting the majority of the outgassing composition, and the majority impurities released were CO and CO2. Furthermore, samples pre-baked at 900 °C exhibit lower impurity levels, with the outgassing rate per unit area of impurity (CO) being less than 10–10 Pa·m3·s−1·m-2, implying that the high-temperature pre-baking treatment facilitates the decomposition of organic molecules and enhances the diffusion of internal gases, thereby further reducing in the outgassing rate of B4C. This study demonstrates that B4C treated with rigorous processes can serve as main shielding material in the vacuum chamber of ITER devices, providing valuable reference for the selection of shielding material of future fusion reactors.
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.