Changes in global and edge plasma parameters (H (98(y,2)), dimensionless collisionality nu *, core density peaking, separatrix density n (e,sep)) with variations in the D-2 fueling rate and divertor configuration are unified into a single trend when mapped to ⟨T (e,ot)⟩, the spatially averaged spectroscopically derived outer target electron temperature. Dedicated JET with the ITER-like wall (JET-ILW) experiments in combination with an extended JET-ILW database of unseeded low-triangularity H-mode plasmas spanning a wide range of D-2 fueling rates, I (p), B (t) and heating power have demonstrated the importance of ⟨T (e,ot)⟩ as a key physics parameter linking the recycling particle source and detachment with plasma performance. The remarkably robust H (98(y,2)) trend with ⟨T (e,ot)⟩ is connected to a strong inverse correlation between ⟨T (e,ot)⟩, n (e,sep) and nu *, thus directly linking changes in the divertor recycling moderated by ⟨T (e,ot)⟩ with the previously established relationship between nu *, core density peaking and core pressure resulting in a degradation in core plasma performance with decreasing ⟨T (e,ot)⟩ (increasing nu *). A strong inverse correlation between the separatrix to pedestal density ratio, n (e,sep)/n (e,ped), and ⟨T (e,ot)⟩ is also established, with the rise in n (e,sep)/n (e,ped) saturating at ⟨T (e,ot)⟩ > 10 eV. A strong reduction in H (98(y,2)) is observed as ⟨T (e,ot)⟩ is driven from 30 to 10 eV via additional D-2 gas fueling, while the divertor remains attached. Consequently, the pronounced performance degradation in attached divertor conditions has implications for impurity seeding radiative divertor scenarios, in which H (98(y,2)) is already low (similar to 0.7) before impurities are injected into the plasma since moderate gas fueling rates are required to promote high divertor neutral pressure. A favorable pedestal pressure, p (e,ped), dependence on I (p) has also been observed, with an overall increase in p (e,ped) at I (p) = 3.4 MA as ⟨T (e,ot)⟩ is driven down from attached to high-recycling divertor conditions. In contrast, p (e,ped) is reduced with decreasing ⟨T (e,ot)⟩ in the lower I (p) branches. Further work is needed to (i) clarify the potential role of edge opacity on the observed favorable pedestal pressure I (p) scaling; as well as to (ii) project the global and edge plasma performance trends with ⟨T (e,ot)⟩ to reactor-scale devices to improve predictive capability of the coupling between recycling and confined plasma fueling in what are foreseen to be more opaque edge plasma conditions.

Experimental study on the role of the target electron temperature as a key parameter linking recycling to plasma performance in JET-ILW

Vianello N;Rubino G;Uccello A;
2022

Abstract

Changes in global and edge plasma parameters (H (98(y,2)), dimensionless collisionality nu *, core density peaking, separatrix density n (e,sep)) with variations in the D-2 fueling rate and divertor configuration are unified into a single trend when mapped to ⟨T (e,ot)⟩, the spatially averaged spectroscopically derived outer target electron temperature. Dedicated JET with the ITER-like wall (JET-ILW) experiments in combination with an extended JET-ILW database of unseeded low-triangularity H-mode plasmas spanning a wide range of D-2 fueling rates, I (p), B (t) and heating power have demonstrated the importance of ⟨T (e,ot)⟩ as a key physics parameter linking the recycling particle source and detachment with plasma performance. The remarkably robust H (98(y,2)) trend with ⟨T (e,ot)⟩ is connected to a strong inverse correlation between ⟨T (e,ot)⟩, n (e,sep) and nu *, thus directly linking changes in the divertor recycling moderated by ⟨T (e,ot)⟩ with the previously established relationship between nu *, core density peaking and core pressure resulting in a degradation in core plasma performance with decreasing ⟨T (e,ot)⟩ (increasing nu *). A strong inverse correlation between the separatrix to pedestal density ratio, n (e,sep)/n (e,ped), and ⟨T (e,ot)⟩ is also established, with the rise in n (e,sep)/n (e,ped) saturating at ⟨T (e,ot)⟩ > 10 eV. A strong reduction in H (98(y,2)) is observed as ⟨T (e,ot)⟩ is driven from 30 to 10 eV via additional D-2 gas fueling, while the divertor remains attached. Consequently, the pronounced performance degradation in attached divertor conditions has implications for impurity seeding radiative divertor scenarios, in which H (98(y,2)) is already low (similar to 0.7) before impurities are injected into the plasma since moderate gas fueling rates are required to promote high divertor neutral pressure. A favorable pedestal pressure, p (e,ped), dependence on I (p) has also been observed, with an overall increase in p (e,ped) at I (p) = 3.4 MA as ⟨T (e,ot)⟩ is driven down from attached to high-recycling divertor conditions. In contrast, p (e,ped) is reduced with decreasing ⟨T (e,ot)⟩ in the lower I (p) branches. Further work is needed to (i) clarify the potential role of edge opacity on the observed favorable pedestal pressure I (p) scaling; as well as to (ii) project the global and edge plasma performance trends with ⟨T (e,ot)⟩ to reactor-scale devices to improve predictive capability of the coupling between recycling and confined plasma fueling in what are foreseen to be more opaque edge plasma conditions.
2022
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
Inglese
62
6
066030-1
066030-13
13
https://iopscience.iop.org/article/10.1088/1741-4326/ac5668/meta
Sì, ma tipo non specificato
recycling impact on plasma performance
integration of tokamak exhaust and performance
experimental
plasma divertor spectroscopy
Electronic ISSN: 1741-4326 - 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. This work was also supported by the US DOE under Contract No. DE-AC05-00OR22725 with UT-Battelle, LLC. This scientific paper has been published as part of the international project co-financed by the Polish Ministry of Science and Higher Education within the programme called PMW for 2021.
24
info:eu-repo/semantics/article
262
Lomanowski, B; Dunne, M; Vianello, N; Aleiferis, S; Brix, M; Canik, J; Carvalho, I S; Frassinetti, L; Frigione, D; Garzotti, L; Groth, M; Meigs, A; Me...espandi
01 Contributo su Rivista::01.01 Articolo in rivista
restricted
   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/20.500.14243/444585
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