中性束注入到泰国托卡马克-1快离子研究的模拟

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-10-03 DOI:10.1016/j.fusengdes.2025.115455

Apiwat Wisitsorasak , Kunihiro Ogawa , Siriyaporn Sangaroon , Boonyarit Chatthong , Akihiro Shimizu , Worathat Paenthong , Suebsak Suksaengpanomrung , Arlee Tamman , Nopporn Poolyarat , Mitsutaka Isobe

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引用次数: 0

摘要

使用蒙特卡罗代码NUBEAM对中性束注入（NBI）进行了模拟，以评估中性束注入的利用率。该研究考察了各种注入条件，包括光束能量和方向。结果表明，以共流方向发射的20 keV、切向半径为0.55 ~ 0.65 m的波束适合于泰国托卡马克-1。结合环面场（TF）纹波，模拟结果表明，由于香蕉漂移损失和∇B漂移效应，大多数束流离子逃离了相邻两个TF线圈之间区域的最后封闭通量面（LCFS）。此外，基于VMEC代码重建的三维平衡态，利用AE3D代码计算了alfv录影带的本征模态。分析表明，间隙频率出现在130 ~ 300 kHz范围内。在边带共振条件下，激发TAE模式所需的最小光束能量为2 keV。

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Simulation of neutral beam injection towards fast ion study in Thailand Tokamak-1

Simulations of neutral beam injection (NBI) are performed using the Monte Carlo code NUBEAM to assess NBI utilization. The study investigates various injection conditions, including beam energy and direction. Results indicate that a 20 keV beam launched in the co-current direction with a tangential radius of 0.55–0.65 m is suitable for Thailand Tokamak-1. Incorporating the toroidal field (TF) ripple, the simulations show that most beam ions escape the last closed flux surface (LCFS) in the region between two adjacent TF coils due to banana drift loss and

\nabla B

drift effect. Furthermore, Alfvén eigenmodes are computed using the AE3D code, based on three-dimensional equilibria reconstructed by the VMEC code. The analysis reveals that the gap frequencies occur within the range of 130–300 kHz. The minimum beam energy required to excite the TAE modes is 2 keV at the sideband resonance condition.

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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.