Improvement of plasma discharge performance at KTM tokamak

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

Fusion Engineering and Design Pub Date : 2024-10-10 DOI:10.1016/j.fusengdes.2024.114684

B. Chektybayev , I. Tazhibayeva , E. Batyrbekov , Ye. Kashikbayev , D. Olkhovik , D. Zarva , S. Zhunisbek , A. Duisen , A. Zhaksybayeva , A. Lee , V. Pavlov , V. Dokuka , R. Khayrutdinov

引用次数: 0

Abstract

The paper presents the results of experimental campaigns conducted in 2022–2023 aimed at improving and enhancing plasma discharge parameters at the KTM tokamak. The experiments achieved a plasma current of approximately 500 kA in a limiter configuration, with a discharge duration of up to 2 s. Plasma discharges were obtained in the ohmic heating mode. The results described in the paper represent the next step toward achieving the plasma discharge design parameters for the KTM.

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提高 KTM 托卡马克的等离子体放电性能

本文介绍了 2022-2023 年开展的旨在改进和提高 KTM 托卡马克等离子体放电参数的实验活动的结果。实验在限制器配置下实现了约 500 kA 的等离子体电流，放电持续时间长达 2 秒。论文中描述的结果代表了实现 KTM 等离子体放电设计参数的下一步。

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.