9 results on '"Tsalas, Maximos"'
Search Results
2. Charged particle dynamics in sheared magnetic reversals with application to the earth's magnetotail
- Author
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Tsalas, Maximos Georgios
- Subjects
538.7 ,Field - Published
- 2000
3. MINT, an ITER Tool for Interactive Visualization of Data
- Author
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Abadie, Lana, Carannante, Giuseppe, Kalsi, Sukhmeet Singh, Makowski, Dariusz, Mazur, Piotr, Neto, Andre, Nunes, Isabel, Panchumarti, Jaswant, Perek, Piotr, Pinches, Simon, Simrock, Stefan, and Tsalas, Maximos
- Subjects
User Interfaces and User eXperience (UX) ,Accelerator Physics - Abstract
ITER will produce large volumes of data that need to be visualized and analyzed. This paper describes the development of a graphical data visualization and exploration tool, MINT (Make Informative and Nice Trends), for plant engineers, operators and physicists. It describes the early development phase from requirements capture to first release covering the mistakes, lessons learnt and future steps. The requirements were collected by interviewing the various stakeholders. The initial neglect of the architecture and user-friendliness turned out to be key points when developing such a tool for a project with a long lifetime like ITER. Modular architecture and clear definition of generic interfaces (abstraction layer) is crucial for such a long lifetime project and makes it ready for future adaptations to new plotting, processing and GUI libraries. The MINT application is based upon the development of an independent plotting library, which acts as a wrapper to the underlying graphical library. This allows scientists and engineers to develop their own specific tools, which are immune to changes of graphical library. The development based on Python uses Qt5 as the visual backend., Proceedings of the 18th International Conference on Accelerator and Large Experimental Physics Control Systems, ICALEPCS2021, Shanghai, China
- Published
- 2022
- Full Text
- View/download PDF
4. First plasma operation of the enhanced JET vertical stabilisation system
- Author
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Rimini, Fernanda G., Crisanti, Flavio, Albanese, Raffaele, Ambrosino, Giuseppe, Ariola, Marco, Artaserse, Giovanni, Bellizio, Teresa, Coccorese, Vincenzo, De Tommasi, Gianmaria, De Vries, Peter, Lomas, Peter J., Maviglia, Francesco, Neto, Andre, Nunes, Isabel, Pironti, Alfredo, Ramogida, Giuseppe, Sartori, Filippo, Shaw, Stephen R., Tsalas, Maximos, Vitelli, Riccardo, and Zabeo, Luca
- Published
- 2011
- Full Text
- View/download PDF
5. Modelling of combined ICRF and NBI heating in JET hybrid plasmas
- Author
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Gallart Dani, Mantsinen Mervi, Challis Clive, Frigione Domenico, Graves Jonathan, Hobirk Joerg, Belonohy Eva, Czarnecka Agata, Eriksson Jacob, Goniche Marc, Hellesen Carl, Jacquet Philippe, Joffrin Emmanuel, Krawczyk Natalia, King Damian, Lennholm Morten, Lerche Ernesto, Pawelec Ewa, Sips George, Solano Emilia, Tsalas Maximos, and Valisa Marco
- Subjects
Physics ,QC1-999 - Abstract
During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high performance plasma scenarios envisaged for ITER operation. In this paper we model the combined ICRF+NBI heating in selected key hybrid discharges using PION. The antenna frequency was tuned to match the cyclotron frequency of minority hydrogen (H) at the center of the tokamak coinciding with the second harmonic cyclotron resonance of deuterium. The modelling takes into account the synergy between ICRF and NBI heating through the second harmonic cyclotron resonance of deuterium beam ions which allows us to assess its impact on the neutron rate RNT. We evaluate the influence of H concentration which was varied in different discharges in order to test their role in the heating performance. According to our modelling, the ICRF enhancement of RNT increases by decreasing the H concentration which increases the ICRF power absorbed by deuterons. We find that in the recent hybrid discharges this ICRF enhancement was in the range of 10-25%. Finally, we extrapolate the results to D-T and find that the best performing hybrid discharges correspond to an equivalent fusion power of ∼7.0 MW in D-T.
- Published
- 2017
- Full Text
- View/download PDF
6. The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield
- Author
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Mantsinen Mervi, Challis Clive, Frigione Domenico, Graves Jonathan, Hobirk Joerg, Belonohy Eva, Czarnecka Agata, Eriksson Jacob, Gallart Dani, Goniche Marc, Hellesen Carl, Jacquet Philippe, Joffrin Emmanuel, King Damian, Krawczyk Natalia, Lennholm Morten, Lerche Ernesto, Pawelec Ewa, Sips George, Solano Emilia R., Tsalas Maximos, and Valisa Marco
- Subjects
Physics ,QC1-999 - Abstract
Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997. The current plans for JET include new experiments with deuterium-tritium (D-T) plasmas with more ITER-like conditions given the recently installed ITER-like wall (ILW). In the 2015-2016 campaigns, significant efforts have been devoted to the development of high-performance plasma scenarios compatible with ILW in preparation of the forthcoming D-T campaign. Good progress was made in both the inductive (baseline) and the hybrid scenario: a new record JET ILW fusion yield with a significantly extended duration of the high-performance phase was achieved. This paper reports on the progress with the hybrid scenario which is a candidate for ITER longpulse operation (∼1000 s) thanks to its improved normalized confinement, reduced plasma current and higher plasma beta with respect to the ITER reference baseline scenario. The combined NBI+ICRF power in the hybrid scenario was increased to 33 MW and the record fusion yield, averaged over 100 ms, to 2.9x1016 neutrons/s from the 2014 ILW fusion record of 2.3x1016 neutrons/s. Impurity control with ICRF waves was one of the key means for extending the duration of the high-performance phase. The main results are reviewed covering both key core and edge plasma issues.
- Published
- 2017
- Full Text
- View/download PDF
7. A first analysis of JET plasma profile based indicators for disruption prediction and avoidance
- Author
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Pau Alessandro, Fanni Alessandra, Murari Andrea, Cannas Barbara, Rimini Fernanda, Pisano Gianluca, Sias Giuliana, JET Contributors, Baruzzo Matteo, Tsalas Maximos, Sparapani Paolo, and de Vries Peter
- Subjects
disruption prediction ,JET ,nuclear fusion - Abstract
Disruptive events still pose a serious problem for the protection of in-vessel components of large size tokamak devices, representing therefore a key aspect to be considered for the design of next step fusion devices such as ITER and DEMO. If an efficient mitigation is strongly required to avoid damage and preserve the structural integrity of the machine, efficient avoidance schemes are needed to possibly bring the plasma back to a safe operating condition. In this framework, disruption prediction plays a key role and in the last few years a substantial effort has been devoted to developing more sophisticated prediction systems and improving their performance both in terms of success rate and warning time. Many of the presently developed disruption predictors mainly rely on MHD markers related to still rotating modes and, especially, to locked modes, which are basically the final precursor of most of the disruptions. Nevertheless, in many cases the detection warning time is still unsatisfactory with respect to avoidance requirements, and a significant step forward needs to be taken. This work deals with the development of "plasma profile based indicators" for disruption prediction and avoidance in JET, where parameterized peaking factors have been implemented for electron temperature, density and plasma radiation profiles. The basic interplay of the time evolution of different profiles will be described in relation to the phenomenology characterizing specific disruption types together with the relevant time scales. Furthermore, a statistical analysis aiming to describe differences and boundaries between the safe and the disruptive space as well as among specific types of disruptions will be presented, discussing the implications in terms of disruption prediction and avoidance. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission and the ITER Organization.
- Published
- 2017
8. The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield
- Author
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Barcelona Supercomputing Center, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Gallart, Dani, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, King, Damian, Krawczyk, Natalia, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia R., Tsalas, Maximos, Valisa, Marco, JET Contributors, Barcelona Supercomputing Center, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Gallart, Dani, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, King, Damian, Krawczyk, Natalia, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia R., Tsalas, Maximos, Valisa, Marco, and JET Contributors
- Abstract
Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997. The current plans for JET include new experiments with deuterium-tritium (D-T) plasmas with more ITER-like conditions given the recently installed ITER-like wall (ILW). In the 2015-2016 campaigns, significant efforts have been devoted to the development of high-performance plasma scenarios compatible with ILW in preparation of the forthcoming D-T campaign. Good progress was made in both the inductive (baseline) and the hybrid scenario: a new record JET ILW fusion yield with a significantly extended duration of the high-performance phase was achieved. This paper reports on the progress with the hybrid scenario which is a candidate for ITER longpulse operation (∼1000 s) thanks to its improved normalized confinement, reduced plasma current and higher plasma beta with respect to the ITER reference baseline scenario. The combined NBI+ICRF power in the hybrid scenario was increased to 33 MW and the record fusion yield, averaged over 100 ms, to 2.9x1016 neutrons/s from the 2014 ILW fusion record of 2.3x1016 neutrons/s. Impurity control with ICRF waves was one of the key means for extending the duration of the high-performance phase. The main results are reviewed covering both key core and edge plasma issues., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission., Peer Reviewed, Postprint (published version)
- Published
- 2017
9. Modelling of combined ICRF and NBI heating in JET hybrid plasmas
- Author
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Barcelona Supercomputing Center, Gallart, Dani, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, Krawczyk, Natalia, King, Damian, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia, Tsalas, Maximos, Valisa, Marco, JET Contributors, Barcelona Supercomputing Center, Gallart, Dani, Mantsinen, Mervi, Challis, Clive, Frigione, Domenico, Graves, Jonathan, Hobirk, Joerg, Belonohy, Eva, Czarnecka, Agata, Eriksson, Jacob, Goniche, Marc, Hellesen, Carl, Jacquet, Philippe, Joffrin, Emmanuel, Krawczyk, Natalia, King, Damian, Lennholm, Morten, Lerche, Ernesto, Pawelec, Ewa, Sips, George, Solano, Emilia, Tsalas, Maximos, Valisa, Marco, and JET Contributors
- Abstract
During the 2015-2016 JET campaigns many efforts have been devoted to the exploration of high performance plasma scenarios envisaged for ITER operation. In this paper we model the combined ICRF+NBI heating in selected key hybrid discharges using PION. The antenna frequency was tuned to match the cyclotron frequency of minority hydrogen (H) at the center of the tokamak coinciding with the second harmonic cyclotron resonance of deuterium. The modelling takes into account the synergy between ICRF and NBI heating through the second harmonic cyclotron resonance of deuterium beam ions which allows us to assess its impact on the neutron rate RNT. We evaluate the influence of H concentration which was varied in different discharges in order to test their role in the heating performance. According to our modelling, the ICRF enhancement of RNT increases by decreasing the H concentration which increases the ICRF power absorbed by deuterons. We find that in the recent hybrid discharges this ICRF enhancement was in the range of 10-25%. Finally, we extrapolate the results to D-T and find that the best performing hybrid discharges correspond to an equivalent fusion power of ∼7.0 MW in D-T., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Dani Gallart would like to thank “La Caixa” for support of his PhD studies., Peer Reviewed, Postprint (published version)
- Published
- 2017
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