The gyro oscillators or simply gyrotrons are used in a variety of applications where high electromagnetic power is required at millimeter/submillimeter wave frequencies. The research on the gyrotron microwave tube was initiated by the demand of high power, high frequency electromagnetic wave source in the magnetically confined plasma fusion application. Since the initial phase of gyrotron development, new thrust areas have been explored by the several research groups. The gyrotron shows several unique advantages as a high power source compare to the other millimeter/submillimeter wave sources either semiconductor based devices or vacuum based tube devices. At present gyrotron is used successfully in the field of plasma heating, plasma diagnosis, medical spectroscopy, material processing, whether monitoring etc. discussed in detail in this article. Several new fields of technology like security, metal joining, planetary defense etc. are under exploration for the futuristic use of gyrotron. In this review article, the applications of gyrotron, various issues remained in the further modification of the device, global scenario of the gyrotron development are discussed in detail.

A Review on the Applications of High Power, High Frequency Microwave Source: Gyrotron

https://pure.mpg.de/pubman/item/item_2573928_5/component/file_2574793/Poli_TORBEAM.pdf

TORBEAM 2.0, a paraxial beam tracing code for electron-cyclotron beams in fusion plasmas for extended physics applications

Sawtooth control using electron cyclotron current drive (ECCD) has been demonstrated in ITER-like plasmas with a large fast ion fraction, wide q = 1 radius and long uncontrolled sawtooth period in DIII-D. The sawtooth period is minimized when the ECCD resonance is just inside the q = 1 surface. Sawtooth destabilization using driven current inside q = 1 avoids the triggering of performance-degrading neoclassical tearing modes (NTMs), even at much higher pressure than required in the ITER baseline scenario. Operation at βN = 3 without 3/2 or 2/1 NTMs has been achieved in ITER demonstration plasmas when sawtooth control is applied using only modest ECCD power. Numerical modelling qualitatively confirms that the achieved driven current changes the local magnetic shear sufficiently to compensate for the stabilizing influence of the energetic particles in the plasma core.

/pdf/sawtooth-control-using-electron-cyclotron-current-drive-in-1pk932hwab.pdf

Sawtooth control using electron cyclotron current drive in ITER demonstration plasmas in DIII-D

Das Institut fur Hochleistungsimpuls- und Mikrowellentechnik (IHM) arbeitet auf dem Gebiet der Hochleistungsimpuls- und Hochleistungsmikrowellentechnologie. Sowohl die Forschung und Entwicklung von Hochleistungsquellen als auch die damit verbundenen Anwendungen stehen im Fokus.

/pdf/annual-report-2016-institute-for-pulsed-power-and-microwave-124lskrdb0.pdf

Annual Report 2016 / Institute for Pulsed Power and Microwave Technology / Institut für Hochleistungsimpuls- und Mikrowellentechnik. (KIT Scientific Reports ; 7745)

Enhancement of the output power per gyrotron has been planned in the Large Helical Device (LHD). Three 77-GHz gyrotrons with an output power of more than 1 MW have been operated. In addition, a high power gyrotron with the frequency of 154 GHz (1 MW/5 s, 0.5 MW/CW) was newly installed in 2012, and the total injection power of Electron cyclotron resonance heating (ECRH) reached 4.6 MW. The operational regime of ECRH plasma on the LHD has been extended due to the upgraded ECRH system such as the central electron temperature of 13.5 keV with the line-averaged electron density ne_fir = 1 × 1019 m−3. The electron thermal confinement clearly improved inside the electron internal transport barrier, and the electron thermal diffusivity reached neoclassical level. The global energy confinement time increased with increase of ne_fir. The plasma stored energy of 530 kJ with ne_fir = 3.2 × 1019 m−3, which is 1.7 times larger than the previous record in the ECRH plasma in the LHD, has been successfully achieved.

Extension of high Te regime with upgraded electron cyclotron resonance heating system in the Large Helical Device

Progress in the ITER electron cyclotron system development

The ITER Ion Cyclotron Heating and Current Drive system will deliver 20 MW of radio frequency power to the plasma in quasi continuous operation during the different phases of the experimental programme. The system also has to perform conditioning of the tokamak first wall at low power between main plasma discharges. This broad range of requirements imposes a high flexibility and a high availability. The paper highlights the physics and design requirements on the IC system, the main features of its subsystems, the predicted performance, and the current procurement and installation schedule.

Status of the ITER EC H&CD system

The EU will be providing the largest contribution to the ITER electron cyclotron (EC) heating and current drive (H&CD) system (20 MW, CW at 170 GHz). The contribution includes one third of the H&CD gyrotrons, their associated power supplies and four upper port launcher antennas. In all areas of participation, the EU EC partnership (coordinated by the European Fusion Development Agreement) aims toward advancing the technology, while staying within a specified cost envelope. This is portrayed in the co-axial gyrotron development that offers the potential to double the output power per source (2.0 MW), increasing the delivered power for a fixed number of auxiliary systems. The EU partnerships also attempt to increase performance for the entire EC system, in particular the launching antennas. The proposed front steering launcher design offers greater control of MHD activity than the previous remote steering design and opens up the possibility of an enhanced performance UL. The EC physics requirements are repartitioned between the upper and equatorial launchers for a synergetic balance, which increases the EC physics capabilities while relaxing some of the engineering requirements.

/pdf/eu-developments-of-the-iter-ecrh-system-45tnnsi4jq.pdf

EU developments of the ITER ECRH system

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Progress in the ITER electron cyclotron system development

Status of the ITER EC H&CD system

EU developments of the ITER ECRH system