Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET

Bernert, M.; Wischmeier, M.; Huber, A.; Reimold, F.; Lipschultz, B.; Lowry, C.; Brezinsek, S.; Dux, R.; Eich, T.; Kallenbach, A.; Lebschy, A.; Maggi, C. F.; McDermott, R. M.; Pütterich, T.; Wiesen, S.; Contributors, Jet; Team, EUROfusion Mst

doi:10.1016/j.nme.2016.12.029

Cited by 110 publications

(95 citation statements)

References 25 publications

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“…They resulted in a noise budget for signal cables of 0.3-3 µV/m which was achieved by some cable prototypes tested. Bolometer measurements at ASDEX Upgrade and JET also show noise levels in this range [11]. Comparing this to the values of Fig.…”

Section: Estimated Los Intensitiessupporting

confidence: 68%

“…Furthermore, two cameras on the divertor cassettes are used to observe the plasma edge on the HFS and the remaining 18 cameras can be distributed to cover further regions of interest (e.g. between X-point and HFS for observation of MARFEs (radiation instabilities) or radiation patterns in high radiative scenarios with varying location [11]), provide LOS to assess potential toroidal asymmetry in the radiation profile as well as to provide redundancy to account for potential failures during life-time. The full picture of the proposed LOS distribution in the divertor is shown in Fig.…”

Section: Optimisation Of Losmentioning

confidence: 99%

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Performance estimations for the ITER bolometer diagnostic

Meister

Penzel

Szabo-Balint

et al. 2019

Fusion Engineering and Design

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The ITER bolometer diagnostic shall provide the measurement of the total radiation emitted from the plasma, a part of the overall energy balance. Up to 550 lines-of-sight (LOS) will be installed in ITER observing the whole plasma from many different angles to enable reliable measurements and tomographic reconstructions of the spatially resolved radiation profile. The performance of the diagnostic is intimately linked to the constraints imposed by the design requirements, the sensor and data acquisition design, as well as expected noise levels.The results presented contain the estimated signal intensities for the current design and integration of bolometer cameras in ITER, based on the simulated radiation profile for the ITER standard scenario (DT-plasma at 15 MA, 500 MW with low impurity content). The corresponding power deposited onto the absorber ranges between 0.5 µW and 2 mW. The expected noise levels derived mainly from lab measurements and compared to operating bolometer systems yield estimated values for ITER in the order of 1 µW, clearly indicating a need for optimizing the diagnostic.The optimization potential is discussed. Cameras for which the light yield could be increased are identified. Also, the potential for enhancing the sensitivity by using different absorber thicknesses is explored.

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Section: Estimated Los Intensitiessupporting

confidence: 68%

Section: Optimisation Of Losmentioning

confidence: 99%

Performance estimations for the ITER bolometer diagnostic

Meister

Penzel

Szabo-Balint

et al. 2019

Fusion Engineering and Design

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show abstract

“…Reduction of the heat flux density on plasma facing components to a technically feasible level is one of the most challenging issues for magnetic confinement fusion devices on the path to a reactor. A promising approach is the creation of a controlled impurity radiation zone in the vicinity of the plasma-surface-interaction (PSI) area by means of a divertor [1][2][3][4][5][6][7][8]. The basic idea of a divertor configuration [9][10][11] is to separate the PSI region from the plasma confinement region by establishing an appropriate separatrix-bounded magnetic configuration.…”

mentioning

confidence: 99%

First Observation of a Stable Highly Dissipative Divertor Plasma Regime on the Wendelstein 7-X Stellarator

et al. 2019

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“…High radiation scenarios with detached divertor targets were observed at AUG [9][10][11] and JET [12,13] with different seeded gases such as krypton, nitrogen, and neon. While Kr increases the radiated power in the core and unfavorably reduces the core confinement, both N and Ne seems to efficiently increase the radiation in the SOL and can be used to achieve the detachment [14,15]. N seems to retain and radiate in the divertor region and slightly affect the core confinement.…”

Section: Introductionmentioning

confidence: 99%

Testing of the SOLPS-ITER code at Globus-M2 spherical tokamak with detached divertor

et al. 2018

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In according to a present understanding of Scrape-Off Layer (SOL) physics, future thermonuclear devices like ITER, DEMO and beyond, require high radiation regimes in order to reduce heat loads on tokamak divertor. Recent experiments at ASDEX Upgrade, JET and other tokamaks demonstrated that such regimes might be achieved by the seeding of the radiative impurities. In the present paper the modeling of the high radiation regimes and the transition to the detachment at the Globus-M2 spherical tokamak is performed by the SOLPS-ITER transport code. The obtained modeling results for GLobus-M2 tokamak demonstrate the trend similar to what is observed at larger machines, e.g. AUG and JET. The significant reduction of peak power density at the outer target plate and transition to the detachment with High Field Side High Density (HFSHD) formation at the inner plate was achieved with impurity seeding rate almost equal to the deuterium puff (in el/sec). However, unlike AUG, further increasing of the seeding rate leads not to a formation of the radiative X-point, but to a radiative collapse. This is caused by smaller machine size, which allows the impurity neutrals to penetrate easier into the confined region. It was noticed that starting with attached divertor the inner target transits to the detachment earlier than the outer one.

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Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET

Cited by 110 publications

References 25 publications

Performance estimations for the ITER bolometer diagnostic

Performance estimations for the ITER bolometer diagnostic

First Observation of a Stable Highly Dissipative Divertor Plasma Regime on the Wendelstein 7-X Stellarator

Testing of the SOLPS-ITER code at Globus-M2 spherical tokamak with detached divertor

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