Preparation of KSTAR pellet injection system for advanced plasma scenarios

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

Fusion Engineering and Design Pub Date : 2025-04-28 DOI:10.1016/j.fusengdes.2025.115121

SooHwan Park, HyunMyung Lee, JaeIn Song, InSik Woo, KwangPyo Kim, KapRai Park

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引用次数: 0

Abstract

The 20 Hz pellet injection system (PIS) was installed at KSTAR (Korea Superconducting Tokamak Advanced Research) in 2016. The pellet injector has already demonstrated its ability to continuously produce deuterium ice rods and inject pellets at a frequency of 20 Hz for up to 300 s. This system allows for the injection of pellets with varying sizes, velocities, and frequencies, enabling a wide range of plasma experiments at KSTAR. As KSTAR advances toward more complex and high-performance plasma scenarios—incorporating modified PFCs (plasma-facing components) and enhanced heating systems—the pellet injection system must be upgraded accordingly. To support these developments, the PIS underwent maintenance and optimization. Following these improvements, the system achieved reliable pellet injection at approximately 200 m/s across various frequencies, with an operational reliability exceeding 95 %. The density profile during injection was monitored using the TCI (two-color interferometer) system. This paper discusses the current status of the pellet injection system following its regular maintenance and performance tests during plasma experiments. Additionally, we outline plans for further enhancements, including improvements to the vacuum pumping system to support the evolving plasma operation requirements at KSTAR.

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先进等离子体场景下KSTAR颗粒注射系统的制备

2016年，在韩国超导托卡马克先进研究所（KSTAR）安装了20赫兹颗粒注入系统（PIS）。颗粒注入器已经证明了其连续生产氘冰棒的能力，并以20赫兹的频率注入颗粒，持续时间长达300秒。该系统允许注入不同尺寸、速度和频率的颗粒，使KSTAR能够进行广泛的等离子体实验。随着KSTAR向更复杂和高性能的等离子体场景发展，包括改进的pfc（等离子体面组件）和增强的加热系统，颗粒注入系统必须相应升级。为了支持这些发展，PIS进行了维护和优化。经过这些改进，该系统在各种频率下以大约200米/秒的速度实现了可靠的颗粒注入，运行可靠性超过95%。使用TCI（双色干涉仪）系统监测注射过程中的密度分布。本文通过对颗粒注入系统的定期维护和等离子体实验中的性能测试，讨论了颗粒注入系统的现状。此外，我们概述了进一步增强的计划，包括改进真空泵系统，以支持KSTAR不断发展的等离子体操作要求。

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.