Achieving high-performance conditions and maximizing the fusion yield of plasma discharges have been one of the main goals of recent Joint European Torus (JET) campaigns in preparation for its second deuterium-tritium (D-T) campaign. The simulations shown in this work delve into the role of external heating using neutral beam injection (NBI) and radio-frequency waves in the ion cyclotron range of frequencies (ICRF) in order to optimise high fusion performance in the JET tokamak. A baseline discharge with record neutron rate is used as a reference in order to perform a D-T prediction, which considers the NBI+RF synergy. In this work, our focus is on JET's two main minority schemes, H and 3He. This study tackles the heating mechanisms by which these schemes reach high-performance conditions. The H scheme typically boosts the ICRF fusion enhancement through the second D harmonic heating, whereas 3He minority is characterised by its strong bulk ion heating. Both features are beneficial for increasing the fusion yield. Nevertheless, the minority concentration is a relevant parameter, which needs to be assessed to understand in which concentration ranges the benefits of each particular minority scheme are met. Therefore, the main objective of this work is to assess in which concentration range the ICRF fusion enhancement and bulk ion heating are optimal, for H and 3He, respectively. Under these conditions, our prediction suggests 3He concentration should stay above 1.2% and H should remain below 2.2%.

Prediction of ICRF minority heating schemes for JET D-T experiments

Nocente M;
2022

Abstract

Achieving high-performance conditions and maximizing the fusion yield of plasma discharges have been one of the main goals of recent Joint European Torus (JET) campaigns in preparation for its second deuterium-tritium (D-T) campaign. The simulations shown in this work delve into the role of external heating using neutral beam injection (NBI) and radio-frequency waves in the ion cyclotron range of frequencies (ICRF) in order to optimise high fusion performance in the JET tokamak. A baseline discharge with record neutron rate is used as a reference in order to perform a D-T prediction, which considers the NBI+RF synergy. In this work, our focus is on JET's two main minority schemes, H and 3He. This study tackles the heating mechanisms by which these schemes reach high-performance conditions. The H scheme typically boosts the ICRF fusion enhancement through the second D harmonic heating, whereas 3He minority is characterised by its strong bulk ion heating. Both features are beneficial for increasing the fusion yield. Nevertheless, the minority concentration is a relevant parameter, which needs to be assessed to understand in which concentration ranges the benefits of each particular minority scheme are met. Therefore, the main objective of this work is to assess in which concentration range the ICRF fusion enhancement and bulk ion heating are optimal, for H and 3He, respectively. Under these conditions, our prediction suggests 3He concentration should stay above 1.2% and H should remain below 2.2%.
2022
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
Inglese
64
12
125006-1
125006-11
11
https://iopscience.iop.org/article/10.1088/1361-6587/ac9925/meta
Sì, ma tipo non specificato
JET
plasma heating
D-T prediction
ICRH
Electronic ISSN: 1361-6587 - http://www.scopus.com/inward/record.url?eid=2-s2.0-85142347586&partnerID=q2rCbXpz - 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 and 2019-2020 under Grant Agreement No. 633053.
1
info:eu-repo/semantics/article
262
Gallart D.; Mantsinen M.J.; Manyer J.; Planas E.; Taylor D.M.A.; Garcia J.; Frigione D.; Garzotti L.; Kim H.T.; Nocente M.; Rimini F.; Van Eester D....espandi
01 Contributo su Rivista::01.01 Articolo in rivista
none
   Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium
   EUROfusion
   H2020
   633053
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/412490
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