Cavity design and interaction computation of a tri-frequency 42-85-94 GHz gyrotron

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

Fusion Engineering and Design Pub Date : 2025-09-18 DOI:10.1016/j.fusengdes.2025.115443

Ravinder Beemagani , S. Yuvaraj , A.K. Jha , M.V. Kartikeyan

引用次数: 0

Abstract

This article presents the design of RF interaction assembly of a gyrotron proposed for generating millimeter waves at three distinct frequencies: 42 GHz, 85 GHz, and 94 GHz. The gyrotron is designed to deliver an output power exceeding 200 kW at each frequency, with an efficiency of approximately 40%. These frequencies are chosen to support various RF heating and sensing requirements of nuclear fusion tokamak systems. RF behavior analysis carried out in this work includes: mode-selection procedure, cold cavity analysis, single-mode analysis and time-dependent multi-mode analysis. The analyses and design are performed using our in-house software package Gyrotron Design Studio (GDS V. 2024). Comprehensive numerical simulations are carried out to design the interaction cavity geometry and determine the nominal beam parameters for supporting multi-frequency operation.

查看原文本刊更多论文

42-85-94 GHz三频回旋管腔体设计与相互作用计算

本文介绍了一种用于产生三种不同频率（42 GHz、85 GHz和94 GHz）毫米波的回旋管的射频相互作用组件的设计。回旋管的设计是在每个频率上提供超过200千瓦的输出功率，效率约为40%。选择这些频率是为了支持核聚变托卡马克系统的各种射频加热和传感要求。本工作中进行的射频行为分析包括：模式选择程序、冷腔分析、单模分析和时变多模分析。分析和设计使用我们的内部软件包Gyrotron design Studio （GDS V. 2024）进行。进行了全面的数值模拟，设计了相互作用腔的几何形状，确定了支持多频率工作的标称光束参数。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

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.