Pellet fragmentation studies for the ITER disruption mitigation system

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Gábor Kocsis , Gergely Bartók , Attila Buzás , Gábor Cseh , Dániel Dunai , Gábor Gárdonyi , Sándor Hegedűs , Marcell Málics , Domonkos Nagy , Dániel Réfy , Tamás Szepesi , Márton Vavrik , Erik Walcz , Sándor Zoletnik , Stefan Jachmich , Uron Kruezi , Michael Lehnen
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Abstract

The thermal and mechanical loads during disruptions are a major threat for large reactor-class tokamak devices. Therefore, shattered pellet injection (SPI) is selected as the baseline technology for the ITER Disruption Mitigation System (DMS). The aim of DMS Support Laboratory located at the HUN-REN Centre for Energy Research is to study the production, launch and shattering of cryogenic protium, deuterium, and neon pellets in the ITER geometry. This paper reports on the fragment analysis procedure and the first results of the fragment plume investigation performed with pellets made of the above materials and accelerated to a speed ranging between 70 and 500m/s. The experimental results show that the fragment plume consists of macroscopic and microscopic fragments. The shattering of about 500 m/s protium and deuterium pellets resulted in a most common fragment size of a few millimeters, while at lower velocities around 250m/s still the same few millimeters size fragments dominate but larger fragments have a higher proportion in the mass distribution. At low velocities (70 m/s) for neon pellets most of the pellet mass was converted into large fragments (from 10 to 20 mm ). The results are also compared with the Parks pellet fragmentation model.
ITER干扰减缓系统的颗粒碎裂研究
中断期间的热负荷和机械负荷是大型反应堆级托卡马克装置的主要威胁。因此,选择破碎颗粒注入(SPI)作为ITER干扰缓解系统(DMS)的基线技术。位于湖南能源研究中心的DMS支持实验室的目的是研究ITER几何结构中低温质子、氘和氖颗粒的产生、发射和破碎。本文报道了用上述材料制成的弹丸加速到70 - 500m/s的速度进行碎片分析过程和碎片羽流调查的初步结果。实验结果表明,碎片羽流由宏观碎片和微观碎片组成。在约500 m/s的速度下,质子和氘球团的破碎导致最常见的碎片尺寸为几毫米,而在250m/s左右的较低速度下,仍然以几毫米大小的碎片为主,但较大的碎片在质量分布中所占的比例更高。在较低的速度下(70米/秒),大多数的氖颗粒质量被转化成大的碎片(从10到20毫米)。结果还与Parks颗粒破碎模型进行了比较。
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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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