Overview of the FTU results

Pucella, G.; Alessi, E.; Amicucci, L.; Angelini, B.; Apicella, M. L.; Apruzzese, G.; Artaserse, G.; Belli, F.; Bin, W.; Boncagni, L.; Botrugno, A.; Briguglio, S.; Bruschi, A.; Buratti, P.; Calabrò, G.; Cappelli, Mauro; Cardinali, A.; Castaldo, C.; Causa, F.; Ceccuzzi, S.; Centioli, C.; Cesario, R.; Cianfarani, C.; Claps, G.; Cocilovo, V.; Cordella, F.; Crisanti, F.; D'Arcangelo, O.; Angeli, M. De; Troia, C. Di; Esposito, B.; Farina, D.; Figini, L.; Fogaccia, G.; Frigione, D.; Fusco, V.; Gabellieri, L.; Garavaglia, S.; Giovannozzi, E.; Granucci, G.; Иафрати, М.; Iannone, F.; Lontano, M.; Maddaluno, G.; Magagnino, S.; Marinucci, M.; Marocco, D.; Mazzitelli, G.; Mazzotta, C.; Milovanov, Alexander V.; Minelli, D.; Mirizzi, F.; Moro, A.; Nowak, S.; Pacella, D.; Panaccione, L.; Panella, M.; Pericoli‐Ridolfini, V.; Pizzuto, A.; Podda, S.; Ramogida, G.; Ravera, G.; Ricci, D.; Романо, А.; Sozzi, C.; Tuccillo, A. A.; Tudisco, O.; Viola, B.; Vitale, V.; Vlad, G.; Zerbini, M.; Zonca, F.; Aquilini, M.; Cefali, P.; Ferdinando, E. Di; Giovenale, S. Di; Giacomi, G.; Grosso, Andrea; Mellera, V.; Mezzacappa, Maria Aparecida; Pensa, A.; Petrolini, P.; Piergotti, V.; Raspante, B.; Rocchi, G.; Sibio, A.; Tilia, B.; Tulli, R.; Vellucci, M.; Zannetti, D.; Radović, Iva Bogdanović; Carnevale, D.; Casolari, A.; Ciotti, Marco; Conti, Claudia; Dincă, P.; Dolci, V.; Galperti, C.; Gospodarczyk, M.; Grosso, G.; Lubiako, L.; Lungu, M.; Martin-Solís, J.R.; Meineri, C.; Murtas, F.; Nardone, A.; Orsitto, F.; Cippo, E. Perelli; Popović, Ž.; Ripamonti, Diego; Simonetto, A.; Tartari, U.

doi:10.1088/1741-4326/aa6239

Cited by 7 publications

(6 citation statements)

References 27 publications

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“…The principal goal of employing a divertor configuration is to reduce the particle-wall interaction, where the charged particles strike the divertor surface well away from the main plasma. The foremost objective of ADITYA-U is to prepare the physics and the technological base for future ITER and DEMO machines by performing dedicated experiments, such as the generation and control of RE, disruption prediction and mitigation studies, and plasma position control and confinement improvement studies with shaped plasmas [9][10][11][12].…”

Section: Introductionmentioning

confidence: 99%

Overview of operation and experiments in the ADITYA-U tokamak

et al. 2019

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First indigenously built tokamak ADITYA, operated over 2 decades with circular poloidal limiter has been upgraded to a tokamak named ADITYA Upgrade for the purpose having shape plasma operation with open divertor geometry. Experiment research in ADITYA-U has made significant progress, since last FEC 2016. After installation of PFC and standard tokamak diagnostics, the Phase-I plasma operations were conducted from December 2016 with graphite toroidal belt limiter. Purely Ohmic discharges in circular plasmas supported by Filament pre-ionization was obtained. The plasma parameters, Ip ~ 80-95 kA, duration ~ 80-180 ms with toroidal field (max.) ~ 1T and chord-averaged electron density ~ 2.5 x 10^19 m^-3 has been achieved. Being a medium sized tokamak, runaway electron (RE) generation, transport and mitigation experiments have always been one of the prime focus of ADITYA-U. MHD activities and density enhancement with H2 gas puffing studied. The Phase-I operation was completed in March 2017. The Phase-II operation preparation in ADITYA-U includes calibration of magnetic diagnostics followed by commissioning of major diagnostics and installation of baking system. After repeated cycles of baking the vacuum vessel up to ~ 130°C, the Phase-II operations resumed from February 2018 and are continuing to achieve plasma parameters close to the design parameters of circular limiter plasmas using real time plasma position control. Hydrogen gas breakdown was observed in more than ~2000 discharge including Phase-I and Phase-II operation without a single failure. Several experiments, including the primary RE control with lower E/P operation and secondary RE control with fuelling of Supersonic Molecular Beam Injection as well as sonic H2 gas puffing during current flat-top and Neon gas puffing for better plasma confinement are undergoing. The dismantling of ADITYA and reassembling of ADITYA-U along with experimental results of Phase-I and Phase-II operations from ADITYA-U will be discussed.

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Section: Introductionmentioning

confidence: 99%

Overview of operation and experiments in the ADITYA-U tokamak

et al. 2019

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“…However, an accurate ECH RE source model is not yet available. Experimental evidence of such a source has been reported [41,42]. On the other hand, auxiliary heating in general might also provide a beneficial effect by augmenting the plasma temperature and hence decreasing its resistivity and thus the required E during the current ramp-up, which aspect is shown in more detail in section 4.…”

Section: Survey Of Re Experiencesmentioning

confidence: 95%

“…KSTAR and WEST are the only existing tokamaks in this study that makes use of super-conducting magnets, as ITER will also deploy in the future. Several of these devices have reported over the years, individual studies on specifically startup RE, such as notably FTU [39][40][41][42][43], JET [5,31,44,45], to some extend also C-MOD [46], NSTX [47] and recently WEST [48][49][50][51][52]. Other notable references to start-up RE from devices, not included in this particular study are [25,26,30,33,36,53,54].…”

Section: Multi-device Comparisonmentioning

confidence: 99%

“…The efficiency of this RE source compared to primary or secondary generation is generally not yet well understood. However, comparing FTU discharges with similar values of E/E D , thus likely a similar primary generation level, but with or without ECH power, showed that those with ECH power produced more RE [41,42]. However, experiments also show that the application of ECH, generally results in lower levels of E/E D in general, due to the higher plasma temperatures.…”

Section: The Effect Of Auxiliary Heatingmentioning

confidence: 99%

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Cross-machine comparison of runaway electron generation during tokamak start-up for extrapolation to ITER

et al. 2023

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A cross-machine comparison of global parameters that determine the Runaway Electron (RE) generation and loss process during tokamak start-up was carried out with the aim to extrapolate these to ITER. The study found that all considered discharges, also those that do not show signs of RE, are non-thermal at the start, i.e. have a streaming parameter larger than 0.1. During the current ramp-up the electric field, E, remains above the critical value, Ec, that allows RE in the plasma. The distinction to be made is not if RE can form but, if sufficient RE can form fast enough such that they are detected or start to dominate the dynamics of the tokamak discharge. The dynamics of the value of E, density and temperature during tokamak are key to the formation of RE. It was found that larger devices operate with E closer to Ec, due to their higher temperatures, hence the RE generation is relatively slower. The slower time scales for the formation of RE, estimated to be of the order of 100s of ms in ITER simplifies the development of avoidance schemes. The RE confinement time is also an important determinant of the entire process and is found to increase with the device size. The study also revealed that drift orbit losses, a mechanism often attributed as the main RE loss mechanism during the early tokamak discharge, are actually more difficult to achieve. RE losses might be more likely attributed to RE diffusion due to magnetic turbulence.

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“…Such issues can be studied in detail in dedicated programs in smaller experiments that permit the realization of relevant scenarios involving significant fractions of REs. [2][3][4] In this context, the recent integration of different diagnostics 5 and new software tools within the FTU real-time RE control system 6,7 is contributing to the characterization of RE dynamics 8 to the study of effective mitigation strategies 9 and to the design of control-oriented dynamical models of current, horizontal, and vertical displacement for REs in the postdisruption phase. 10 A specific activity was focused on the design, development, and construction of a new plasma diagnostic, referred to as REIS (RE Imaging and Spectroscopy system) to detect and study in-flight REs.…”

Section: Introductionmentioning

confidence: 99%

Runaway electron imaging spectrometry (REIS) system

Causa

Gospodarczyk

Buratti

et al. 2019

Review of Scientific Instruments

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A portable Runaway Electron Imaging and Spectrometry System (REIS) was developed in ENEA-Frascati to measure synchrotron radiation spectra from in-flight runaway electrons in tokamaks. The REIS is a wide-angle optical system collecting simultaneously visible and infrared emission spectra using an incoherent bundle of fibers, in a spectral range that spans from 500 nm to 2500 nm, and visible images using a CCD color microcamera at a rate of 25 frames/s. The REIS system is supervised and managed using a dedicated LabVIEW program to acquire data simultaneously from three spectrometers every 20 ms (configurable down to 10 ms). An overview of the REIS architecture and acquisition system and resulting experimental data obtained in FTU are presented and discussed in this paper.

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Overview of the FTU results

Cited by 7 publications

References 27 publications

Overview of operation and experiments in the ADITYA-U tokamak

Overview of operation and experiments in the ADITYA-U tokamak

Cross-machine comparison of runaway electron generation during tokamak start-up for extrapolation to ITER

Runaway electron imaging spectrometry (REIS) system

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