First operation and validation of simulations for the divertor cryo-vacuum pump in Wendelstein 7-X

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
V. Haak , C.P. Dhard , D. Boeyaert , T. Bräuer , V. Bykov , C. Day , S. Degenkolbe , G. Ehrke , J. Igitkhanov , M. Khokhlov , T. Kremeyer , M. Nagel , D. Naujoks , M. Pietsch , D. Pilopp , G. Schlisio , H. Strobel , C. Tantos , S. Varoutis , H. Viebke , O. Volzke
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引用次数: 0

Abstract

Ten cryo-vacuum pumps (CVPs) were installed in the subdivertor region of each island divertor in the stellarator Wendelstein 7-X (W7-X) and operated for the first time during the recently completed plasma campaign OP2.1. A pumping speed of 70 ± 1 m3s was measured during dedicated tests with known hydrogen gas injection. Based on a conductance model, the estimated pumping speed ranges from 86-93 m3s for different sticking coefficients between 0.6 and 0.8. After completion of the initial tests the CVPs were operated successfully throughout the campaign, with regeneration performed once a week. Neutral gas pressures in the subdivertor in the range of 10−4 mbar are well within the molecular flow regime and limit the particle exhaust capabilities of the CVPs. Simulations of the neutral gas pressure in the three-dimensional complex geometry of the subdivertor were performed using the DIVGAS code based on the direct simulation Monte Carlo method and a model implemented in the steady-state thermal package in ANSYS, which are in agreement with the measured values during plasma operation.

文德尔施泰因 7-X 分流器低温真空泵的首次运行和模拟验证
在恒星器温德斯坦7-X(W7-X)的每个岛形分流器的分流器区域安装了十个低温真空泵(CVP),并在最近完成的等离子体运动OP2.1期间首次运行。在已知氢气注入的专门测试中,测得的泵送速度为 70 ± 1 m3s。根据电导模型,在 0.6 和 0.8 之间的不同粘滞系数下,估计抽速范围为 86-93 立方米/秒。在完成初步测试后,CVP 在整个活动期间成功运行,每周进行一次再生。分馏器中的中性气体压力在 10-4 毫巴范围内,完全处于分子流状态,限制了 CVP 的颗粒排气能力。使用基于直接模拟蒙特卡洛法的 DIVGAS 代码和 ANSYS 稳态热软件包中的模型,对子掺混器三维复杂几何形状中的中性气体压力进行了模拟,结果与等离子体运行期间的测量值一致。
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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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