Experimental Results of Core Ion Temperature and Neutral Density Measurements on ADITYA Tokamak using Four Channels Neutral Particle Analyzer

Kumar, Ajay; Pandya, Santosh P.

doi:10.1007/s10894-020-00245-6

Cited by 4 publications

(1 citation statement)

References 33 publications

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“…In recent years, the tokamak has been upgraded to so-called ADITYA-Upgrade (ADITYA-U) [14] for better plasma operations and physics studies. The main plasma and machine parameters of ADITYA-U tokamak are tabulated in table 1 [15][16][17][18][19]. To establish the lower hybrid power coupling and current drive, a passive-active multi-junction (PAM) antenna is designed and fabricated [20].…”

Section: Motivationmentioning

confidence: 99%

Conceptual design of multichannel fast electron bremsstrahlung detection system to study fast electron dynamics during lower hybrid current drive in ADITYA-U tokamak

2023

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To drive plasma current non inductively, a Lower Hybrid Current Drive (LHCD) system with a passive-active multijunction (PAM) antenna for injecting lower hybrid wave (LHWs) has been designed, fabricated and to be integrated with ADITYA-U Tokamak. A fast electron population in the energy range of a few keV to several hundreds of keV is generated with the injection of the LHWs. These fast electrons interacting mainly with ions and electrons result in Hard X-Ray (HXR) emission called Fast Electron Bremsstrahlung acronym as FEB emission. A single channel FEB detection system is being used in the earlier experiment of LHCD in ADITYA-U tokamak. However, the single channel detection system can't provide a radial emissivity profile of HXR intensity distribution. In order to determine a radial emissivity profile, for the first time, a multichannel FEB detection system is designed for ADITYA-U tokamak. This paper describes the detailed conceptual design for the selection of suitable detectors, optimization of the collimators, shielding geometry, and low energy filtering cut-off. In the present design analysis, the soller collimator concept is considered over a simple pinhole camera system due to its several advantages. In order to optimize the multichannel FEB system parameters for the best possible performance, a forwarded modelling code has been used. The signal to background ratio at each detector location has been estimated for a few system parameters and reported herein.

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Section: Motivationmentioning

confidence: 99%

Conceptual design of multichannel fast electron bremsstrahlung detection system to study fast electron dynamics during lower hybrid current drive in ADITYA-U tokamak

2023

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Efficiency of hydrogen beam electron stripping using various stripping gases for neutral particle analysis in MEPhIST tokamak

Bulgadaryan

Sinelnikov

Efimov

2022

Nuclear Instruments and Methods in Physics Research Section B:

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Overview of physics results from the ADITYA-U tokamak and future experiments

Tanna,

Ghosh,

Jadeja

et al. 2024

Nucl. Fusion

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The ADITYA Upgrade (ADITYA-U), a medium-sized (R_0=75 cm,a=25 cm) conventional tokamak facility in India, has been consistently producing experiments findings by using circular and shaped-plasmas. Recognizing the plasma parameters aligning closely with the design parameters of circular limited plasmas, ADITYA-U shifted its focus toward exploring the operational regime for experimentation on saw-tooth and MHD phenomena. Moreover, ADITYA-U has made consistent advancements toward conducting preliminary plasma shaping experiments through the activation of top and bottom divertor coils utilizing hydrogen as well as deuterium fuels. Confinement is improved by a factor of ~ 1.5 in D_2 plasmas when compared to H_2 plasmas of ADITYA-U. Further, ADITYA-U operations emphasize preventing disruptions and runaway electrons (REs) to ensure safe operations for future fusion devices. Significant suppression of REs has been achieved in ADITYA-U with the application of pulsed localized vertical magnetic field (LVF) perturbation, thereby establishing the technique's independence from the tokamak device. The successful RE mitigation requires a critical threshold of LVF pulse magnitude, which is approximately 1% of the toroidal magnetic field, and a minimum duration of ~ 5 ms. Apart from this, several novel findings have been achieved in the ADITYA-U experiments, including the modification of sawtooth duration through gas-puff, the emergence of MHD-induced GAM-like oscillations, the propagation of fast heat pulses induced by MHD activity, the control of RE dynamics through Gas-puffs, the propagation of pinch-driven cold-pulses, the transport and core accumulations of argon impurities, the mass dependency of plasma toroidal rotation and the detection of “RICE” scaling, as well as the characterization of edge plasma using wall conditioning methods, such as glow discharge cleaning using a combination of Ar-H2 mixture, localized wall cleaning by Electron Cyclotron (EC) resonant plasma, and the development of machine learning-based disruption predictions, will be discussed in this paper.

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Experimental Results of Core Ion Temperature and Neutral Density Measurements on ADITYA Tokamak using Four Channels Neutral Particle Analyzer

Cited by 4 publications

References 33 publications

Conceptual design of multichannel fast electron bremsstrahlung detection system to study fast electron dynamics during lower hybrid current drive in ADITYA-U tokamak

Conceptual design of multichannel fast electron bremsstrahlung detection system to study fast electron dynamics during lower hybrid current drive in ADITYA-U tokamak

Efficiency of hydrogen beam electron stripping using various stripping gases for neutral particle analysis in MEPhIST tokamak

Overview of physics results from the ADITYA-U tokamak and future experiments

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