Initial plasma achieved within engineering constraints in the PLATO tokamak

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
T. Nishizawa , Y. Nagashima , C. Moon , D. Nishimura , T.-K. Kobayashi , T. Ido , T. Suetsugu , T. Tokuzawa , K. Yamasaki , T. Yamada , S. Inagaki , T. Onchi , S. Kato , M. Murayama , T. Kobayashi , A. Shimizu , K. Kikuta , R. Hayashi , D. Di Matteo , A. Fujisawa
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引用次数: 0

Abstract

In order to save flux consumption and lessen engineering requirements, the achievable toroidal loop voltage tends to be lowered in modern tokamaks. In such devices, careful optimization of the plasma startup scenario is often required to achieve a successful tokamak discharge. The PLATO tokamak, which is recently built at Kyushu University, also faces challenges in the plasma startup. PLATO employs an air-cored central solenoid that limits the loop voltage and creates stray magnetic fields. In addition, only simple capacitor banks with modest maximum charging voltages are available for the generation of the poloidal magnetic and toroidal electric fields in the initial operation. To realize the breakdown and plasma current ramp-up under those constraints, the configuration of coils and capacitor bank settings has been optimized to produce sufficient loop voltage while minimizing the stray field inside the vacuum chamber at the onset of the discharge. Through this optimization, a tokamak discharge with a plasma current of 30 kA and a pulse duration of 20 ms has been achieved.
在PLATO托卡马克的工程限制内实现的初始等离子体
为了节省磁通消耗和降低工程要求,现代托卡马克的可实现环面电压趋于降低。在这种装置中,通常需要仔细优化等离子体启动场景以实现成功的托卡马克放电。最近在九州大学建造的PLATO托卡马克在等离子体启动方面也面临挑战。PLATO采用了一个空心的中央螺线管来限制回路电压并产生杂散磁场。此外,在初始运行中,只有具有适度最大充电电压的简单电容器组可用于产生极向磁场和环向电场。为了在这些限制条件下实现击穿和等离子体电流的上升,优化了线圈和电容器组的配置,以产生足够的环路电压,同时最小化放电开始时真空室内的杂散场。通过这种优化,实现了等离子体电流为30 kA、脉冲持续时间为20 ms的托卡马克放电。
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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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