Scenario development for D–T operation at JET

Garzotti, L.; Challis, C.; Dümont, R.; Frigione, D.; Graves, J. P.; Lerche, E.; Mailloux, J.; Mantsinen, M.; Rimini, F.; Casson, F. J.; Czarnecka, A.; Eriksson, J.; Felton, R.; Frassinetti, L.; Gallart, D.; García, J.; Giroud, C.; Joffrin, E.; Kim, Hyun-Tae; Krawczyk, N.; Lennholm, M.; Lomas, P. J.; Lowry, C.; Meneses, L.; Nunes, I.; Roach, C. M.; Romanelli, M.; Sharapov, S. E.; Silburn, S.; Sips, A. C. C.; Štefániková, E.; Tsalas, M.; Valcárcel, D.; Valovič, M.; Contributors, Jet

doi:10.1088/1741-4326/ab1cca

Cited by 62 publications

(100 citation statements)

References 34 publications

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“…2003), JET (Garzotti et al . 2019), Alcator C-Mod (Marmar & Alcator C-Mod Group 2007), SPARC V2 (Creely et al . 2020), ITER (Casper et al .…”

Section: Discussionunclassified

“…(Hughes et al 2018) and ASDEX-Upgrade (Kallenbach et al 2015). In preparation for DTE2, JET has also started to approach ∼31 MW • T m −1 , assuming 0 % core radiation (Garzotti et al 2019). For the SPARC V2 full field, full current, DT H-mode, the normalized power of P SOL B 0 /R 0 ∼ 191 MW • T m −1 (assuming 39 % core radiation fraction) is, thus, significantly higher than in present-day devices and approaches levels for proposed fusion pilot plants, such as ARC, where P SOL B 0 /R 0 ∼ 256 MW • T m −1 (assuming the nominal 35 % core radiation fraction) (Kuang et al 2018).…”

Section: Divertor Design Guidelines For Sparcmentioning

confidence: 99%

“…This highlights the importance of intermediary devices such as SPARC V2 and ITER for reducing the uncertainty in developing design guidelines for a future fusion pilot plant. SPARC will be (Streibl et al 2003), JET (Garzotti et al 2019), Alcator C-Mod (Marmar & Alcator C-Mod Group 2007), SPARC V2 , ITER (Casper et al 2013) and ARC (Kuang et al 2018). Note that the maximum conducted power (P SOL,max ) corresponds to the maximum available auxiliary power for the present-day devices whereas for SPARC V2, ITER and ARC it refers to the projections for P SOL assuming no core radiation.…”

Section: Sparc Xpt Divertormentioning

confidence: 99%

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Divertor heat flux challenge and mitigation in SPARC

et al. 2020

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Owing to its high magnetic field, high power, and compact size, the SPARC experiment will operate with divertor conditions at or above those expected in reactor-class tokamaks. Power exhaust at this scale remains one of the key challenges for practical fusion energy. Based on empirical scalings, the peak unmitigated divertor parallel heat flux is projected to be greater than 10 GW m−2. This is nearly an order of magnitude higher than has been demonstrated to date. Furthermore, the divertor parallel Edge-Localized Mode (ELM) energy fluence projections (~11–34 MJ m−2) are comparable with those for ITER. However, the relatively short pulse length (~25 s pulse, with a ~10 s flat top) provides the opportunity to consider mitigation schemes unsuited to long-pulse devices including ITER and reactors. The baseline scenario for SPARC employs a ~1 Hz strike point sweep to spread the heat flux over a large divertor target surface area to keep tile surface temperatures within tolerable levels without the use of active divertor cooling systems. In addition, SPARC operation presents a unique opportunity to study divertor heat exhaust mitigation at reactor-level plasma densities and power fluxes. Not only will SPARC test the limits of current experimental scalings and serve for benchmarking theoretical models in reactor regimes, it is also being designed to enable the assessment of long-legged and X-point target advanced divertor magnetic configurations. Experimental results from SPARC will be crucial to reducing risk for a fusion pilot plant divertor design.

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“…2003), JET (Garzotti et al . 2019), Alcator C-Mod (Marmar & Alcator C-Mod Group 2007), SPARC V2 (Creely et al . 2020), ITER (Casper et al .…”

Section: Discussionunclassified

Section: Divertor Design Guidelines For Sparcmentioning

confidence: 99%

Section: Sparc Xpt Divertormentioning

confidence: 99%

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Divertor heat flux challenge and mitigation in SPARC

et al. 2020

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“…is an ongoing area of work in JET [110,111]). It is very challenging to find a subset with a wide suggests that increasing Ip leads to both increasing ne ped and increasing Te ped .…”

Section: (Ii)mentioning

confidence: 99%

Pedestal structure, stability and scalings in JET-ILW: the EUROfusion JET-ILW pedestal database

et al. 2020

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The EUROfusion JET-ILW pedestal database is described, with emphasis on three main issues. First, the technical aspects are introduced, including a description of the data selection, the datasets, the diagnostics used, the experimental and theoretical methods implemented and the main definitions. Second, the JET-ILW pedestal structure and stability are described. In particular, the work describes the links between the engineering parameters (power, gas and divertor configuration) and the disagreement with the peeling-ballooning (PB) model implemented with ideal MHD equations. Specifically, the work clarifies why the JET-ILW pedestal tends to be far from the PB boundary at high gas and high power, showing that a universal threshold in power and gas cannot be found but that the relative shift (the distance between the position of the pedestal density and of the pedestal temperature) plays a key role. These links are then used to achieve an empirical explanation of the behavior of the JET-ILW pedestal pressure with gas, power and divertor configuration. Third, the pedestal database is used to revise the scaling law of the pedestal stored energy. The work shows a reasonable agreement with the earlier Cordey scaling in terms of plasma current and triangularity dependence, but highlights some differences in terms of power and isotope mass dependence.

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“…The quest for finding new sources of energy has generated large interest in magnetized plasmas where plasma is confined in toroidal device such as tokamaks and stellarators aiming to produce energy through controlled thermonuclear fusion [1,2]. In particular, there is an ongoing effort aimed to better understand the effect of anomalous particle transport in reducing the confinement in magnetized plasma [3].…”

Section: Introductionmentioning

confidence: 99%

A spectroscopical study of H$$_{2}$$ emission in a simply magnetized toroidal plasma

et al. 2021

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A noninvasive diagnostic technique relying on optical emission spectroscopy is used for studying plasma confined in a purely toroidal magnetic field. Visible emission lines of molecular hydrogen were specifically targeted. Bi-dimensional structures and poloidal plasma profiles were reconstructed from the emissivity distribution of hydrogen Fulcher system using a tomographic method. A few details concerning the methods employed to capture different emission viewlines, data reduction and tomographic reconstruction techniques are also addressed. We report also the first measurement of the excitation temperature of the $$\text {H}_2$$ H 2 [3c] level in the center of the plasma column, $$T_{\mathrm{exc}}=0.67 \pm 0.11$$ T exc = 0.67 ± 0.11 eV. Graphic Abstract

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Scenario development for D–T operation at JET

Cited by 62 publications

References 34 publications

Divertor heat flux challenge and mitigation in SPARC

Divertor heat flux challenge and mitigation in SPARC

Pedestal structure, stability and scalings in JET-ILW: the EUROfusion JET-ILW pedestal database

A spectroscopical study of H$$_{2}$$ emission in a simply magnetized toroidal plasma

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