The impact of stray magnetic fields on the KSTAR NBI performance

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

Fusion Engineering and Design Pub Date : 2024-09-02 DOI:10.1016/j.fusengdes.2024.114646

SeulChan Hong , Geonwoo Baek , Jae Young Jang , Byungkeun Na , J.H. Jeong , C.Y. Lee , Min Park , Jaewook Kim , Jong-Gu Kwak , Yong-Su Na

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Abstract

The stray magnetic fields generated by a plasma discharge impact the performance of neutral beam injection (NBI), leading to a decline in the plasma performance of the Korea Superconducting Tokamak Advanced Research (KSTAR). To evaluate the impact of the stray magnetic field on the NBI performance, a Monte Carlo simulation tool was developed. The simulation tool integrates the stray magnetic fields, NBI beam line components, and charge exchange processes comprehensively, allowing for quantitative analysis of the NBI performance reduction due to the stray magnetic fields. The high pressure of the beam chamber, along with the stray magnetic fields, causes a significant reduction of the beam power, emphasizing the need to maintain low vacuum pressure. However, the stray magnetic field does not significantly affect the injection angle of the beam particles reaching the tokamak. Predictive integrated simulations show that the decrease in beam performance due to stray magnetic fields can affect a degradation in plasma performance during long pulse discharge in KSTAR.

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杂散磁场对 KSTAR NBI 性能的影响

等离子体放电产生的杂散磁场会影响中性束注入（NBI）的性能，导致韩国超导托卡马克先进研究（KSTAR）的等离子体性能下降。为了评估杂散磁场对 NBI 性能的影响，开发了一种蒙特卡罗模拟工具。该模拟工具全面整合了杂散磁场、NBI 束线组件和电荷交换过程，可对杂散磁场导致的 NBI 性能降低进行定量分析。束流室的高压以及杂散磁场会导致束流功率显著降低，这就强调了保持低真空压力的必要性。不过，杂散磁场对到达托卡马克的束流粒子的注入角影响不大。预测性综合模拟表明，杂散磁场导致的束流性能下降会影响 KSTAR 长脉冲放电期间等离子体性能的下降。

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.