Progress in the ITER electron cyclotron heating and current drive system design

Omori, T.; Albajar, F.; Bonicelli, T.; Carannante, G.; Cavinato, M.; Cismondi, F.; Darbos, C.; Денисов, Г. Г.; Farina, D.; Gagliardi, Mario; Gandini, F.; Gassmann, T.; Goodman, T.; Hanson, G. R.; Henderson, M.; Kajiwara, K.; McElhaney, Karen; Nousiainen, R.; Oda, Y.; Oustinov, A.; Parmar, Darshankumar; Popov, Vladimir L.; Purohit, D.; Rao, S.L.; Rasmussen, D. A.; Rathod, Vipal; Ronden, D.; Saibene, G.; Sakamoto, K.; Sartori, F.; Scherer, T.; Singh, Narinder; Strauß, D.; Takahashi, Koji

doi:10.1016/j.fusengdes.2014.12.023

Cited by 11 publications

(8 citation statements)

References 4 publications

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“…In contrast to klystrons, the resonance frequency of a gyrotron cavity is not determined by the characteristic size, but by the strength of the magnetic field (see equations ( 2) and ( 7)). According to equation (8), for a given frequency, operation in a high-order mode (determined by its eigenvalue χ m,n ) with low Ohmic attenuation can be selected just by the cavity diameter. Since the Ohmic skin losses are proportional to 1/(χ 2 m,n − m 2 ), volume modes with 0.3 m/χ m,n  0.5 are preferable.…”

Section: Gyrotron Interaction Principlementioning

confidence: 99%

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High-power gyrotrons for electron cyclotron heating and current drive

Thumm¹,

Денисов²,

Sakamoto³

et al. 2019

Nucl. Fusion

141

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In many tokamak and stellarator experiments around the globe that are investigating energy production via controlled thermonuclear fusion, electron cyclotron heating and current drive (ECH&CD) are used for plasma start-up, heating, non-inductive current drive and MHD stability control. ECH will be the first auxiliary heating method used on ITER. Megawatt-class, continuous wave (CW) gyrotrons are employed as high-power millimeter (mm)-wave sources. The present review reports on the worldwide state-of-the-art of high-power gyrotrons. Their successful development during the past years changed ECH from a minor to a major heating method. After a general introduction of the various functions of ECH&CD in fusion physics, especially for ITER, Section 2 will explain the fast-wave gyrotron interaction principle. Section 3 discusses innovations on the components of modern long-pulse fusion gyrotrons (magnetron injection electron gun (MIG), beam tunnel, cavity, quasi-optical output coupler, synthetic diamond output window, single-stage depressed collector) and auxiliary components (superconducting magnets, gyrotron diagnostics, high-power calorimetric dummy loads). Section 4 deals with present megawatt-class gyrotrons for ITER, W7-X, LHD, EAST, KSTAR and JT-60SA, and also includes tubes for moderate pulse length machines as, ASDEX-U, DIII-D, HL-2A, TCV, QUEST and GAMMA-10. In Section 5 the development of future advanced fusion gyrotrons is discussed. These are tubes with higher frequencies for DEMO, multi-frequency (multi-purpose) gyrotrons, stepwise frequency tunable tubes for plasma stabilization, injection-locked and coaxial-cavity multi-megawatt gyrotrons, as well as sub-THz gyrotrons for collective Thomson scattering (CTS). Efficiency enhancement via multi-stage depressed collectors, fast oscillation recovery methods and reliability, availability, maintainability and inspectability (RAMI) will be discussed at the end of this section.

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Section: Gyrotron Interaction Principlementioning

confidence: 99%

“…The requirements on frequency are relatively flexible. For example, in ITER, the same 170 GHz gyrotrons will be used for breakdown as well as heating, current drive and control of the MHD instabilities [8].…”

Section: Introductionmentioning

confidence: 99%

High-power gyrotrons for electron cyclotron heating and current drive

Thumm¹,

Денисов²,

Sakamoto³

et al. 2019

Nucl. Fusion

141

View full text Add to dashboard Cite

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“…13 and 14, respectively [3]. A 10-cm recess from the neighbouring wall-mounted blankets allows using front shield first wall of stainless steel armour instead of beryllium layer for both the EL and ULs.…”

Section: Launchersmentioning

confidence: 99%

Status of the ITER Electron Cyclotron Heating and Current Drive System

Darbos

Albajar

Bonicelli

et al. 2015

J Infrared Milli Terahz Waves

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The electron cyclotron (EC) heating and current drive (H&CD) system developed for the ITER is made of 12 sets of high-voltage power supplies feeding 24 gyrotrons connected through 24 transmission lines (TL), to five launchers, four located in upper ports and one at the equatorial level. Nearly all procurements are in-J Infrared Milli Terahz Waves kind, following general ITER philosophy, and will come from Europe, India, Japan, Russia and the USA. The full system is designed to couple to the plasma 20 MW among the 24 MW generated power, at the frequency of 170 GHz, for various physics applications such as plasma start-up, central H&CD and magnetohydrodynamic (MHD) activity control. The design takes present day technology and extends toward high-power continuous operation, which represents a large step forward as compared to the present state of the art. The ITER EC system will be a stepping stone to future EC systems for DEMO and beyond.The development of the EC system is facing significant challenges, which includes not only an advanced microwave system but also compliance with stringent requirements associated with nuclear safety as ITER became the first fusion device licensed as basic nuclear installations as of 9 November 2012.Since the conceptual design of the EC system was established in 2007, the EC system has progressed to a preliminary design stage in 2012 and is now moving forward toward a final design.

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“…Electron cyclotron resonance heating (ECRH) of the plasma is one of the main methods of auxiliary heating at plasma fusion installations [1][2][3][4][5][6]. It has the following advantages:…”

Section: Introductionmentioning

confidence: 99%

System of Electron Cyclotron Heating at the TRT Tokamak

2021

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Main parameters of the possible system of electron cyclotron resonance heating of the plasma for the compact tokamak with strong magnetic field (TRT) are presented. Preliminary estimates show that, to deposit radiation with calculated power of 10 MW into the plasma at pulse duration of 100 s, 12 1-MW gyrotron complexes will be required that operate at a frequency of 230 GHz. Preliminary calculations of the main components of the system are presented.

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Progress in the ITER electron cyclotron heating and current drive system design

Cited by 11 publications

References 4 publications

High-power gyrotrons for electron cyclotron heating and current drive

High-power gyrotrons for electron cyclotron heating and current drive

Status of the ITER Electron Cyclotron Heating and Current Drive System

System of Electron Cyclotron Heating at the TRT Tokamak

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