The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challenges arising from 37 MW of injected power in the ITER like wall environment, keeping the radiation in the edge and core controlled, avoiding MHD instabilities and reaching high neutron rates. The Deuterium hybrid plasmas have been re-run in Tritium and methods have been found to keep the radiation controlled but not at high fusion performance probably due to time constraints. For the first time this scenario has been run in Deuterium-Tritium (50:50). These plasmas were re-optimised to have a radiation-stable H-mode entry phase, good impurity control through edge Ti gradient screening and optimised performance with fusion power exceeding 10 MW for longer than three alpha particle slow down times, 8.3 MW averaged over 5 s and fusion energy of 45.8 MJ.

The JET hybrid scenario in Deuterium, Tritium and Deuterium-Tritium

Alessi E;Auriemma F;Giacomelli L;Nowak S;Sozzi C;Valisa M;
2023

Abstract

The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with the ITER-like Be/W wall. The development started in pure Deuterium with refinement of the plasma current, and toroidal magnetic field choices and succeeded in solving the heat load challenges arising from 37 MW of injected power in the ITER like wall environment, keeping the radiation in the edge and core controlled, avoiding MHD instabilities and reaching high neutron rates. The Deuterium hybrid plasmas have been re-run in Tritium and methods have been found to keep the radiation controlled but not at high fusion performance probably due to time constraints. For the first time this scenario has been run in Deuterium-Tritium (50:50). These plasmas were re-optimised to have a radiation-stable H-mode entry phase, good impurity control through edge Ti gradient screening and optimised performance with fusion power exceeding 10 MW for longer than three alpha particle slow down times, 8.3 MW averaged over 5 s and fusion energy of 45.8 MJ.
2023
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
Inglese
63
112001-1
112001-27
27
https://iopscience.iop.org/article/10.1088/1741-4326/acde8d/meta
Sì, ma tipo non specificato
magnetic fusion
hybrid scenario
Tritium
D-T
isotope effects
Open Access: Creative Commons Attribution 4.0 licence. This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No. 101052200 - EUROfusion) and from the EPSRC [Grant Number EP/W006839/1].
1
109
info:eu-repo/semantics/article
262
Hobirk, J; Challis, Cd; Kappatou, A; Lerche, E; Keeling, D; King, D; Aleiferis, S; Alessi, E; Angioni, C; Auriemma, F; Baruzzo, M; Belonohy, E; Bernar...espandi
01 Contributo su Rivista::01.01 Articolo in rivista
open
   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/20.500.14243/438334
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