Commissioning of Electron Cyclotron Resonance Heating (ECRH) system on tokamak Aditya-U

Shukla, B. K.; Patel, Jatin; Mistry, Hardik; Patel, Harshida; Purohit, D.; Parmar, K. G.; Babu, Rajan; Ghosh, Joydeep; Tanna, R.L.; Jadeja, K. A.; Patel, Kaushal; Makwana, M.; Gupta, C.N.; Kushwah, M.; Team, Aditya-U

doi:10.1016/j.fusengdes.2019.03.108

Cited by 4 publications

(3 citation statements)

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“…Details of associated electronics, the data acquisition and triggering transmitter and receiver systems of ADITYA-U were described in [1]. A 42 GHz, 500 kW, gyratron-based ECRH system of ADITYA-U was reported in [27].…”

Section: Aditya-u Operations and Experimental Progressmentioning

confidence: 99%

“…For the typical discharges in ADITYA-U, in the absence of any strong pre-ionization, gas breakdown and successful plasma start-up are normally achieved with peak loop voltages of ∼18-20 V (electric field ∼ 4.5 V m −1 ). 42 GHz ECR [27]-assisted low loop voltage (∼10-12 V, electric field ∼ 2.1 V m −1 ) startup has been successfully achieved with waves launched in fundamental O-mode from the low magnetic field side. During this experiment, a maximum plasma current of 177 kA and plasma duration of 330 ms were achieved at a maximum toroidal field operated for 1.44 T. However, the available single gyratron can only be used either for pre-ionisation or for plasma heating in a single discharge.…”

Section: Ghz Ecr Assisted Two Pulse Operation In Aditya-umentioning

confidence: 99%

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Overview of recent experimental results from the ADITYA-U tokamak

Tanna¹,

Macwan²,

Ghosh³

et al. 2022

Nucl. Fusion

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Since the 2018 IAEA-FEC conference, in addition to expanding the parameter horizons of the ADITYA-U machine, emphasis has been given to dedicated experiments on inductively driven particle injection (IPI) for disruption studies, runaway electron (RE) dynamics and mitigation, plasma rotation reversal, radiative-improved modes using Ne and Ar injection, modulation of magneto–hydrodynamic modes, edge turbulence using periodic gas puffs and electrode biasing (E-B). Plasma parameters close to the design parameters of circular plasmas with H2 and D2 as fuel have been realized, and the shaped plasma operation has also been initiated. Consistent plasma discharges having I P ∼ 100–210 kA, t ∼ 300–400 ms, n e ∼ 3–6 × 1019 m−3, core T e ∼ 300–500 eV were achieved with a maximum B T of ∼1.5 T. The enhanced plasma parameters are the outcome of repeated cycles of baking (135 °C), followed by extensive wall conditioning, which includes pulsed glow discharge cleaning in H, He and Ar–H mixture, and lithiumization. A higher confinement time has been observed in D2 compared to H2 plasmas. Furthermore, shaped plasmas are attempted for the first time in ADITYA-U. A first of its kind inductively driven particle injection for disruption mitigation studies has been developed and operated. The injection of solid particles into the plasma core leads to a fast current quench. Two pulses of electron cyclotron resonance wave at 42 GHz are launched in a single discharge: one pulse is used for pre-ionization and the second for heating. In a novel approach, a positively biased electrode is used to confine REs after discharge termination. E-B is also used for controlling the rotation of drift-tearing modes by changing the plasma rotation. Cold pulse propagation and signatures of detachment are observed during the injection of short gas puffs. A correlation between the plasma toroidal rotation and the total radiated power has been observed with neon gas injection-induced improved confinement modes.

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Section: Aditya-u Operations and Experimental Progressmentioning

confidence: 99%

Section: Ghz Ecr Assisted Two Pulse Operation In Aditya-umentioning

confidence: 99%

Overview of recent experimental results from the ADITYA-U tokamak

Tanna¹,

Macwan²,

Ghosh³

et al. 2022

Nucl. Fusion

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“…The characteristics (excitation, propagation, absorption, cutoff, harmonic structure) of electromagnetic waves in magnetized plasmas require precise measurement of the relativistic effects associated with the fast-moving electrons, especially for perpendicularly propagating modes (O-mode, X-mode and Bernstein waves) as they all lie in the electron cyclotron resonance frequency range. These waves are used for electron cyclotron resonance heating and current drive in the tokamaks [1][2][3][4][5][6][7][8][9][10][11][12][13][14][15]. The electromagnetic waves for which the perturbed electric field E 1 is parallel to the ambient magnetic field B 0 (E 1 ∥ B 0 ) and the propagation vector k is perpendicular to the ambient magnetic field (k ⊥ B 0 ) are called the ordinary waves.…”

Section: Introductionmentioning

confidence: 99%

Characteristics of ordinary mode in fully relativistic electron plasma

Khan

Ali

Habib

2020

Plasma Phys. Control. Fusion

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Propagation characteristics (resonances, propagation regions, and cutoffs) of ordinary waves (perpendicularly propagating electromagnetic waves) are studied in a relativistic electron plasma by using the kinetic model. The dispersion relation for the ordinary mode (O-mode) in a relativistic electron plasma is investigated by employing the Maxwell-Boltzmann-Jüttner distribution function. As the integration in the relativistic dispersion relation cannot be done analytically so an approximated value is obtained using the trapezoidal rule. Various modes of propagation for the ordinary waves are observed for each harmonic number n due to the relativistic effects defined by the value η = mc 2 kBTe . We also observe that the high-temperature relativistic plasma environment is more transparent for the O-mode as compared to weakly relativistic and non-relativistic plasma environments. Moreover, the cutoff points are shifted to lower values in the relativistic limit.

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