4.5 Article

Diagnostics, data acquisition and control of the divertor test tokamak experiment

Journal

FUSION ENGINEERING AND DESIGN
Volume 122, Issue -, Pages 365-374

Publisher

ELSEVIER SCIENCE SA
DOI: 10.1016/j.fusengdes.2017.05.118

Keywords

Power exhaust; Plasma control; Diagnostics; Data acquisition

Funding

  1. Euratom research and training programme [633053]

Ask authors/readers for more resources

The system of diagnostics, data acquisition and control foreseen on the Divertor Test Tokamak experiment (DTT) is presented. Conceived in an integrated way, the control system meets the specifications of a fusion experiment devoted to the study of the power exhaust problem in view of DEMO. Diagnostics and feedback control are particularly functional to the need of maintaining the plasma close to equilibrium in situations prone to instabilities where the plasma wall interaction is optimized. Strongly oriented to the exploration of control methods suitable for DEMO, DTT will specifically experiment on physics and engineering model based control systems. Control and data flow schemes are inspired by those of ITER. (C) 2017 Elsevier B.V. All rights reserved.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.5
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

Article Physics, Fluids & Plasmas

SPIDER, the Negative Ion Source Prototype for ITER: Overview of Operations and Cesium Injection

G. Serianni, E. Sartori, R. Agnello, M. Agostini, M. Barbisan, M. Bigi, M. Boldrin, M. Brombin, V. Candeloro, R. Casagrande, S. Dal Bello, M. Dan, B. P. Duteil, M. Fadone, L. Grando, P. Jain, A. Maistrello, I. Mario, R. Pasqualotto, M. Pavei, A. Pimazzoni, C. Poggi, A. Rizzolo, A. Shepherd, M. Ugoletti, P. Veltri, B. Zaniol, P. Agostinetti, D. Aprile, G. Berton, C. Cavallini, R. Cavazzana, M. Cavenago, G. Chitarin, S. Cristofaro, G. Croci, N. Cruz, M. Dalla Palma, R. Delogu, M. De Muri, M. De Nardi, S. Denizeau, F. Fellin, A. Ferro, E. Gaio, C. Gasparrini, A. Luchetta, F. Lunardon, G. Manduchi, N. Marconato, D. Marcuzzi, O. McCormack, R. Milazzo, A. Muraro, T. Patton, N. Pilan, M. Recchia, A. Rigoni-Garola, F. Santoro, B. Segalini, M. Siragusa, M. Spolaore, C. Taliercio, P. Zaccaria, R. Zagorski, L. Zanotto, M. Zaupa, M. Zuin, V. Toigo

Summary: This contribution provides an overview of recent operations and main results of cesium injection in the SPIDER negative ion source. Experiments without cesium injection were conducted to verify operational parameters and determine the operational region, while preliminary cesium experiments showed increased negative ion current and decreased co-extracted electrons, with control parameters influencing beam uniformity. Non-Gaussian tails were identified in the angular distribution perpendicular to beam propagation direction. A major shutdown is planned for late 2021 to address operational issues and make scheduled modifications, aiming to meet ITER requirements.

IEEE TRANSACTIONS ON PLASMA SCIENCE (2023)

Article Physics, Fluids & Plasmas

Parametric study of Alfvenic instabilities driven by runaway electrons during the current quench in DIII-D

A. Lvovskiy, C. Paz-Soldan, N. W. Eidietis, A. Dal Molin, G. H. DeGrandchamp, E. M. Hollmann, J. B. Lestz, C. Liu, M. Nocente, D. Shiraki, X. D. Du

Summary: The dependencies of Alfvenic instabilities driven by runaway electrons (REs) during current quench in DIII-D on plasma and material injection parameters were investigated. The observed instabilities in the frequency range of 0.1-3 MHz are correlated with increased RE loss and may play a role in non-sustained RE beams.

NUCLEAR FUSION (2023)

Article Instruments & Instrumentation

Conceptual design of a GEM (gas electron multiplier) based gas Cherenkov detector for measurement of 17 MeV gamma rays from T(D, γ)5He in magnetic confinement fusion plasmas

O. Putignano, G. Croci, A. Muraro, S. Cancelli, F. Caruggi, G. Gorini, G. Grosso, M. H. Kushoro, G. Marcer, M. Nocente, E. Perelli Cippo, M. Rebai, D. Rigamonti, M. Tardocchi

Summary: The current method for evaluating the fusion power throughput of a deuterium-tritium (DT) reactor relies on determining the absolute number of 14 MeV neutrons produced in the DT plasma. An independent method based on absolute counting of 17 MeV gamma rays produced by the T(D, gamma)He-5 reaction has been developed. This paper presents the development of a scintillating Gas Electron Multiplier (GEM) based pre-amplifier for gamma-ray detection, which is insensitive to neutrons and optimized for use in a neutron-rich environment.

REVIEW OF SCIENTIFIC INSTRUMENTS (2023)

Article Automation & Control Systems

Assessment of initial-state-opacity in live and bounded labeled Petri net systems via optimization techniques

Francesco Basile, Gianmaria De Tommasi, Carlo Motta

Summary: This paper provides a necessary and sufficient condition to check the Initial State Opacity (ISO) in discrete event systems (DES) modeled as bounded and live labeled Petri nets (PNs). The proposed approach enables the assessment of ISO by solving Integer Linear Programming problems efficiently.

AUTOMATICA (2023)

Article Nuclear Science & Technology

Lessons learned after three years of SPIDER operation and the first MITICA integrated tests

D. Marcuzzi, V. Toigo, M. Boldrin, G. Chitarin, S. Dal Bello, L. Grando, A. Luchetta, R. Pasqualotto, M. Pavei, G. Serianni, L. Zanotto, R. Agnello, P. Agostinetti, M. Agostini, D. Aprile, M. Barbisan, M. Battistella, G. Berton, M. Bigi, M. Brombin, V. Candela, V. Candeloro, A. Canton, R. Casagrande, C. Cavallini, R. Cavazzana, L. Cordaro, N. Cruz, M. Dalla Palma, M. Dan, A. De Lorenzi, R. Delogu, M. De Muri, M. De Nardi, S. Denizeau, M. Fadone, F. Fellin, A. Ferro, E. Gaio, C. Gasparrini, F. Gnesotto, P. Jain, A. La Rosa, D. Lopez-Bruna, R. Lorenzini, A. Maistrello, G. Manduchi, S. Manfrin, N. Marconato, I. Mario, G. Martini, R. Milazzo, T. Patton, S. Peruzzo, N. Pilan, A. Pimazzoni, C. Poggi, N. Pomaro, B. Pouradier-Duteil, M. Recchia, A. Rigoni-Garola, D. Rizzetto, A. Rizzolo, F. Santoro, E. Sartori, B. Segalini, A. Shepherd, M. Siragusa, P. Sonato, A. Sottocornola, E. Spada, S. Spagnolo, M. Spolaore, C. Taliercio, P. Tinti, P. Tomsic, L. Trevisan, M. Ugoletti, M. Valente, M. Valisa, F. Veronese, M. Vignando, P. Zaccaria, R. Zagorski, B. Zaniol, M. Zaupa, M. Zuin, M. Cavenago, D. Boilson, C. Rotti, H. Decamps, F. Geli, A. Sharma, P. Veltri, J. Zacks, M. Simon, F. Paolucci, A. Garbuglia, D. Gutierrez, A. Masiello, G. Mico, C. Labate, P. Readman, E. Bragulat, L. Bailly-Maitre, G. Gomez, G. Kouzmenko, F. Albajar, M. Kashiwagi, H. Tobari, A. Kojima, M. Murayama, S. Hatakeyama, E. Oshita, T. Maejima, N. Shibata, Y. Yamashita, K. Watanabe, N. P. Singh, M. J. Singh, H. Dhola, U. Fantz, B. Heinemann, C. Wimmer, D. Wuenderlich, K. Tsumori, G. Croci, G. Gorini, A. Muraro, M. Rebai, M. Tardocchi, L. Giacomelli, D. Rigamonti, F. Taccogna, D. Bruno, M. Rutigliano, S. Longo, S. Deambrosis, E. Miorin, F. Montagner, A. Tonti, F. Panin

Summary: ITER plans to use two heating neutral beam injectors plus an optional one as part of its auxiliary heating and current drive system. The expected power per injector is higher than existing facilities worldwide. To enable this development, a Neutral Beam Test Facility (NBTF) has been established, consisting of two test beds called SPIDER and MITICA. SPIDER focuses on developing and characterizing efficient negative ion sources, while MITICA is a full-scale prototype of the ITER Neutral Beam Injector. The lessons learned from the NBTF implementation and future perspectives are discussed.

FUSION ENGINEERING AND DESIGN (2023)

Article Nuclear Science & Technology

Strategy towards model-based design and testing of the ITER Plasma Control System

Timo Ravensbergen, Luca Zabeo, Peter de Vries, L. Pangione, Wolfgang Treutterer, Gianmaria De Tommasi, Woong-ryol Lee, Taehyun Tak, Anze Zagar

Summary: The ITER PCS requires a systematic and formal design and testing procedure, using a model-based approach. The design team uses the PCSSP and RTF for controller design and implementation, with verification and validation. The PCS design and implementation progress is monitored through the PCSDB.

FUSION ENGINEERING AND DESIGN (2023)

Article Instruments & Instrumentation

Numerical and experimental investigations of a microwave interferometer for the negative ion source SPIDER

R. Agnello, R. Cavazzana, I. Furno, R. Jacquier, R. Pasqualotto, E. Sartori, G. Serianni

Summary: The electron density and co-extracted electrons near the extraction grids are important factors in the operation of negative ion sources for fusion reactors. A 100 GHz heterodyne microwave interferometer is being explored as a possible diagnostic tool for measuring electron density in the plasma extraction region. Despite the challenges posed by the source metal walls and the long distance between the microwave modules and the vacuum vessel, preliminary tests have shown that electron density measurement is possible under certain conditions. The main issue in these tests is the decoupling of the one-pass signal from spurious multipaths generated by microwave beam reflections.

JOURNAL OF INSTRUMENTATION (2023)

Article Engineering, Multidisciplinary

A new hard x-ray spectrometer for runaway electron measurements in tokamaks

A. Dal Molin, M. Nocente, M. Dalla Rosa, E. Panontin, D. Rigamonti, M. Tardocchi, A. Shevelev, E. Khilkevitch, M. Iliasova, L. Giacomelli, G. Gorini, E. Perelli Cippo, F. D'Isa, G. Pautasso, G. Papp, G. Tardini, E. Macusova, J. Cerovsky, O. Ficker, M. Salewski, V Kiptily

Summary: A novel hard x-ray (HXR) spectrometer, called runaway electron gamma-ray detection system, has been developed for measuring bremsstrahlung radiation from runaway electrons in fusion plasmas. The system consists of a 1'x1' LaBr3:Ce scintillator crystal and a photomultiplier tube, providing an energy dynamic range exceeding 20 MeV and an energy resolution of 3% at 661.7 keV. The detector gain remains stable even under severe loads, with a gain shift below 3% at HXR counting rates over 1 MCps. The system's outstanding performance allows unprecedented studies of the time-dependent runaway electron energy distribution function in recent experiments.

MEASUREMENT SCIENCE AND TECHNOLOGY (2023)

Article Physics, Fluids & Plasmas

ORBIT simulations of fast ion power loads on the wall of the Divertor Tokamak Test

Marco Gobbin, Gianluca Spizzo

Summary: Neutral beam injection in tokamaks can result in localized fast ion losses, known as 'hot spots', despite overall losses being low. This paper discusses hot spot formation in the Divertor Tokamak Test (DTT) project, showing that fast ions produce hot spots at the beam injection and exit toroidal angles. However, the power load in these hot spots remains below the tolerance of plasma-facing components.

PLASMA PHYSICS AND CONTROLLED FUSION (2023)

Review Chemistry, Analytical

Advances, Challenges, and Future Perspectives of Microwave Reflectometry for Plasma Position and Shape Control on Future Nuclear Fusion Devices

Bruno Goncalves, Paulo Varela, Antonio Silva, Filipe Silva, Jorge Santos, Emanuel Ricardo, Alberto Vale, Raul Luis, Yohanes Nietiadi, Artur Malaquias, Jorge Belo, Jose Dias, Jorge Ferreira, Thomas Franke, Wolfgang Biel, Stephane Heuraux, Tiago Ribeiro, Gianluca De Masi, Onofrio Tudisco, Roberto Cavazzana, Giuseppe Marchiori, Ocleto D'Arcangelo

Summary: Providing energy from fusion and scaling up the process efficiently and economically is a major challenge in engineering. Plasma Position Reflectometry (PPR) plays an important role in future fusion machines by monitoring plasma position and shape. It uses radar methods in microwave and millimetre wave frequency ranges to measure density profile for plasma control.

SENSORS (2023)

Editorial Material Chemistry, Physical

Newborn alpha particles from proton-boron fusion reactions in magnetically confined plasma

Chiara Bustreo, Roberto Cavazzana

Summary: In a recent article published in Nature Communications, Magee et al. present promising results from a unique experiment conducted in the large helical device (LHD). By injecting high-energy protons into a boron plasma, the researchers were able to generate high-energy alpha particles through proton-boron reactions in a magnetically confined plasma.

JOULE (2023)

Article Nuclear Science & Technology

The new vessel complex for the RFX-mod2 experiment: An effective synergy between fusion research and technological development

Simone Peruzzo, Daniele Aprile, Mauro Dalla Palma, Mauro Pavei, Dario Rizzetto, Andrea Rizzolo, Domenico Abate, Piero Agostinetti, Matteo Agostini, Roberto Andreani, Fabrizio Anselmi, Flavio Battistin, Adriano Bernardi, Marco Bernardi, Giovanni Berton, Paolo Bettini, Marco Angelo Bigi, Matteo Bonotto, Matteo Brombin, Alessandra Canton, Lorella Carraro, Roberto Cavazzana, Luigi Cordaro, Giorgio Corniani, Samuele Dal Bello, Antonio De Lorenzi, Gianluca De Masi, Fabio Degli Agostini, Luca Franchin, Paolo Franz, Giulio Gambetta, Francesco Gnesotto, Luca Grando, Paolo Innocente, Bruno Laterza, Luca Lotto, Stefano Manfrin, Giuseppe Marchiori, Nicolo Marconato, Diego Marcuzzi, Lionello Marrelli, Emilio Martines, Maurizio Moresco, Alberto Novella, Roberto Piovan, Nicola Pomaro, Federico Rossetto, Marco Siragusa, Piergiorgio Sonato, Silvia Spagnolo, Monica Spolaore, Cesare Taliercio, David Terranova, Andrea Tiso, Lauro Trevisan, Matteo Valente, Marco Valisa, Matteo Zaupa, Matteo Zuin

FUSION ENGINEERING AND DESIGN (2023)

Article Nuclear Science & Technology

Conceptual design of the DTT in-vessel equatorial coils

R. Ambrosino, R. Albanese, E. Acampora, A. Castaldo, F. Crisanti, R. Iervolino, A. Lampasi

Summary: For the next generation fusion devices, in-vessel coils are crucial for handling elongated plasmas and alternative configurations, but they are highly sensitive to the vertical unstable mode. A pair of equatorial in-vessel coils connected in anti-series can effectively address the vertical control problem. Independent equatorial coils can also provide fast radial control to protect plasma facing components during fast plasma transients. However, they are vulnerable to induced current during disruptive events. In this paper, a solution for the conceptual design of in-vessel equatorial coils is presented, which ensures control performance and robustness in case of disruption, as demonstrated by simulations.

FUSION ENGINEERING AND DESIGN (2023)

Article Physics, Fluids & Plasmas

Modelling performed for predictions of fusion power in JET DTE2: overview and lessons learnt

J. Garcia, F. J. Casson, L. Frassinetti, D. Gallart, L. Garzotti, H. -t. Kim, M. Nocente, S. Saarelma, F. Auriemma, J. Ferreira, S. Gabriellini, A. Ho, P. Huynh, K. K. Kirov, E. Lerche, M. J. Mantsinen, V. K. Zotta, Z. Stancar, D. M. A. Taylor, D. Van Eester, C. D. Challis, JET Contributors

Summary: For more than a decade, an unprecedented predict-first activity has been carried out to predict fusion power and provide guidance to the DTE2 campaign. It is shown that detailed physics-based predictions are necessary and a combination of different modeling complexities and an extended interplay between modeling and experiment are essential for reliable predictions of D-T plasmas.

NUCLEAR FUSION (2023)

Article Computer Science, Information Systems

Long Short-Term Memory-Based Neural Networks for Missile Maneuvers Trajectories Prediction?

Dario Giuseppe Lui, Gaetano Tartaglione, Francesco Conti, Gianmaria De Tommasi, Stefania Santini

Summary: Due to its extensive applications in different contexts, moving target tracking has become a hot topic in the last years, above all in the military field. This work investigates the capability of deep neural networks, particularly Long-Short Term Memory (LSTM) net, in predicting the missile maneuvering trajectories in a model-free fashion, overcoming the limitations of traditional methods in terms of model uncertainties.

IEEE ACCESS (2023)

No Data Available