在热核实验堆 DMS 支持实验室的试验台上分析颗粒推进剂气体膨胀情况

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-06 DOI:10.1016/j.fusengdes.2024.114635
M. Vécsei , G. Anda , G. Bartók , G. Gárdonyi , S. Jachmich , I. Katona , D. Nagy , D. Oravecz , D. Réfy , T. Szepesi , E. Walcz , A. Zsákai , S. Zoletnik
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引用次数: 0

摘要

本文讨论了对热核实验堆 DMS 支持实验室试验台上气体膨胀的分析。为此,在实验室设计阶段进行了有限元数值模拟。模拟结果与试验台建造完成后获得的实验数据进行了比较。结果表明,数值模拟和实验结果非常吻合。两者都表明加速筒中出现了压力波。这些压力波导致弹丸从筒壁脱离。在模拟中还观察到了超音速,实验结果也间接表明了超音速的存在。讨论了推进剂气体回收室内部推进剂气体膨胀的主要过程,并对在弹丸之前进入试验台飞行管的气体量进行了粗略估计。
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Analysis of pellet propellant gas expansion in the test bench of the ITER DMS Support Laboratory

The analysis of the gas expansion in the test bench of the ITER DMS Support Laboratory is discussed. For this purpose, numerical FEM simulations were performed during the design phase of the laboratory. These are compared with experimental data, that have been obtained after the construction of the test bench was finished. The numerical and experimental results have been found to agree well. Both indicate the emergence of pressure waves in the acceleration barrel. These contribute to the pellet detachment from the barrel wall. Supersonic velocities have been also observed in the simulations, and an indirect indication for their presence has been found in the experimental results. The main processes during the propellant gas expansion inside the propellant gas recovery chamber are discussed, and a rough estimate for the amount of gas entering the flight tube of the test bench before the pellet is presented.

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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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