Conceptual Design of Neutral Beam Injection System for EAST

Hu, Chundong; Team, Nbi

doi:10.1088/1009-0630/14/6/30

Cited by 95 publications

(44 citation statements)

References 5 publications

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“…The first high current ion source is developed and installed on the ion source test bed. The experimental performance of the ion source was tested primarily [7][8][9][10][11]. A high current ion source with new arc chamber is developed and finished the new campaign of performance tests in three weeks.…”

Section: Introductionmentioning

confidence: 99%

Development and conditioning of the high current ion source for the EAST neutral beam injector

Xie

Liu

et al. 2013

Nuclear Instruments and Methods in Physics Research Section A:

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Section: Introductionmentioning

confidence: 99%

Development and conditioning of the high current ion source for the EAST neutral beam injector

Xie

Liu

et al. 2013

Nuclear Instruments and Methods in Physics Research Section A:

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“…The superconducting tokamak EAST [1] has been in operation since 2006; the main auxiliary systems, including neutral beam injection (NBI) [2], lower hybrid current drive (LHCD) [3] and ion cyclotron resonance heating (ICRH) [4] also have been installed. A long pulse ECRH system, which has been designed to meet the requirement of steady-state operation in EAST, has been planned since 2011.…”

Section: ．Introductionmentioning

confidence: 99%

Recent progress of the development of a long pulse 140GHz ECRH system on EAST

Wang

Zhang

et al. 2019

EPJ Web Conf.

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A long pulse ECRH system with a goal of 140GHz 4MW 100~1000s has been developed to meet the requirement of steady-state operation on EAST. Gycom gyrotrons are employed in the No.1 and No.3 systems, CPI gyrotrons are used in the No.2 and No.4 systems. The development of the two Gycom gyrotron systems has been finished. The first short pulse EC wave injection has been demonstrated successfully during the EAST 2015 Spring campaign. In the commissioning and operation towards steadystate operation, 0.4MW 100s has been injected to plasma successfully by using the No.1 system, 4.7keV 102s L-mode and 102s H-mode plasma have been achieved on EAST with the help of ECRH. Recently, a longest pulse of 0.55MW 1000s has been obtained based on calorimetric dummy load measurements on the No.3 gyrotron. The No.2 gyrotron also has been installed and partially tested, 500kW 80s has been demonstrated in the dummy load. The remaining No.4 gyrotron will be ready to test in 2018 or 2019. The whole 4MW system will be completed within two years. The 400s fully non-inductive H-mode operation would be expected in the next four years in the condition of fully tungsten diverter on EAST.

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“…The experimental advanced superconducting tokamak (EAST) [1] has been in operation since 2006; the main auxiliary systems, including neutral beam injection (NBI) [2] , lower hybrid current drive (LHCD) [3] and ion cyclotron resonance heating (ICRH) [4] have also been installed. Since the ECRH scheme has many advantages in magnetic fusion devices, it was developed and studied in the W7-X [5] and LHD [6] stellarators, as well as most tokamaks such as DIII-D [7] , ASDEX [8] , HL-2A [9] and KSTAR [10] , where it has been applied to plasma startup, plasma heating, current density profile control and stabilization of magneto hydrodynamics (MHD) modes etc.…”

Section: Introductionmentioning

confidence: 99%

Development and Preliminary Commissioning Results of a Long Pulse 140 GHz ECRH System on EAST Tokamak (Invited)

Wang

Liu

et al. 2016

Plasma Sci. Technol.

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A long pulse electron cyclotron resonance heating (ECRH) system has been developed to meet the requirements of steady-state operation for the EAST superconducting tokamak, and the first EC wave was successfully injected into plasma during the 2015 spring campaign. The system is mainly composed of four 140 GHz gyrotron systems, 4 ITER-Like transmission lines, 4 independent channel launchers and corresponding power supplies, a water cooling, control & inter-lock system etc. Each gyrotron is expected to deliver a maximum power of 1 MW and be operated at 100-1000 s pulse lengths. The No.1 and No.2 gyrotron systems have been installed. In the initial commissioning, a series of parameters of 1 MW 1 s, 900 kW 10 s, 800 kW 95 s and 650 kW 753 s have been demonstrated successfully on the No.1 gyrotron system based on calorimetric dummy load measurements. Significant plasma heating and MHD instability suppression effects were observed in EAST experiments. In addition, high confinement (H-mode) discharges triggered by ECRH were obtained.

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Conceptual Design of Neutral Beam Injection System for EAST

Cited by 95 publications

References 5 publications

Development and conditioning of the high current ion source for the EAST neutral beam injector

Development and conditioning of the high current ion source for the EAST neutral beam injector

Recent progress of the development of a long pulse 140GHz ECRH system on EAST

Development and Preliminary Commissioning Results of a Long Pulse 140 GHz ECRH System on EAST Tokamak (Invited)

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