Vacuum commissioning and operation result after the KSTAR PFC upgrade

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-06-10 DOI:10.1016/j.fusengdes.2025.115249

Kwangpyo Kim , Hyunmyung Lee , Hyung ho Lee , Koung Moon Kim , Hyunseok Kim , Jeongwon Lee , H. Schamis , E.P. Gilson , Jae-in Song , Nam-yong Joung , Soo-hyeon Park

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引用次数: 0

Abstract

The first vacuum commissioning after the installation of new tungsten mono-block cassette divertor has been successfully conducted in KSTAR. The tungsten divertor has been installed in the lower divertor region to handle the high divertor heat loads up to 10 MW/m². On the one hand, the plasma facing components except for the tungsten divertor in the KSTAR vacuum vessel still consists of graphite tiles. Thus, it was much more challenging to maintain high-quality vacuum condition mainly because of various possible impurity sources inside the vessel compared with previous experiment campaigns. In this paper, the detailed procedure for securing vacuum condition of the KSTAR tokamak after the installation of the new tungsten divertor is presented. The vacuum condition is also examined regarding the plasma start-up and the long-pulse high-performance quality.

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KSTAR PFC升级后的真空调试和运行结果

新钨单块卡式分流器安装后的第一次真空调试已在KSTAR成功进行。钨质导流器安装在下部导流器区域，以处理高达10 MW/m2的高导流器热负荷。一方面，KSTAR真空容器中除钨分流器外，面向等离子体的部件仍由石墨瓦组成。因此，与以往的实验活动相比，保持高质量的真空条件更具挑战性，主要是因为容器内可能存在各种杂质源。本文介绍了KSTAR托卡马克在安装新钨转流器后，确保真空状态的具体步骤。研究了真空条件下等离子体启动和长脉冲性能的影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.