cherab/core: Release v1.2.0

Carr, Morghan M.; Meakins, A.; Tomeš, M.; vsnever,

doi:10.5281/zenodo.3551871

Cited by 3 publications

(4 citation statements)

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“…(b) Power deposition profile along the LFS target. Contribution from radiative processes was calculated with the CHERAB code [33]. As discussed in the main text, the artifact visible close to the separatrix does not influence any of the results discussed in the paper.…”

Section: Detachment Analysismentioning

confidence: 92%

“…We estimate that most of this inconsistency is due to a non-perfect convergence of the energy equations. Residual analysis reveals oscillations which [33]. (b) Power deposition profile along the LFS target.…”

Section: Detachment Analysismentioning

confidence: 99%

“…(a) Power deposition profile along the HFS target. Contribution from radiative processes was calculated with the CHERAB code[33]. (b) Power deposition profile along the LFS target.…”

mentioning

confidence: 99%

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SOLPS-ITER modeling of divertor scenarios for EU-DEMO

et al. 2021

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We developed a first single null divertor scenario for EU-DEMO with the SOLPS-ITER code, including all charge states of D, He and Ar in the simulation and kinetic analysis of the neutral gas, but still leaving out drifts. Our results suggest that a partially detached divertor condition can indeed be obtained, with a corresponding peak heat flux on targets to ≈2 MW m−2, within the expected tolerable steady-state limits. The plasma re-attaches ≈30 cm (measured along the plate) from the low field side strike point deep in the SOL, with a consequent raise in the electron temperature up to ≈16 eV outside the detached region, which requires further analysis to assess a possible role of sputtering, especially considering W self-sputtering. The plasma we developed exhibits Z eff ≈ 1.9 in the core, and a pumping speed a few hundred’s m3 s−1 to maintain steady-state; this points to the need of further studies to better characterize the He accumulation in the core region.

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Section: Detachment Analysismentioning

confidence: 92%

Section: Detachment Analysismentioning

confidence: 99%

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SOLPS-ITER modeling of divertor scenarios for EU-DEMO

et al. 2021

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“…Indeed, the quarterpellet SPIs into degraded H-mode shows good impurity assimilation and radiation fraction. Moreover, the radiation heat flux onto the first wall is obtained by the Raysect/CHERAB code suite integrated within integrated modelling & analysis suite (IMAS) [25,26] and their energy impact is calculated. It is found that the maximum energy impact for the full pellet dual-SPI into the baseline H-mode case exceeds the tolerable limit of the stainless steel near the injector, but stays well below that of the tungsten.…”

Section: Introductionmentioning

confidence: 99%

Plasmoid drift and first wall heat deposition during ITER H-mode dual-SPIs in JOREK simulations

Hu,

Artola,

Nardon

et al. 2024

Nucl. Fusion

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The heat flux mitigation during the Thermal Quench (TQ) by the Shattered Pellet Injection (SPI) is one of the major elements of disruption mitigation strategy for ITER. It's efficiency greatly depends on the SPI and the target plasma parameters, and is ultimately characterised by the heat deposition on to the Plasma Facing Components (PFCs). To investigate such heat deposition, JOREK simulations of neon-mixed dual-SPIs into ITER baseline H-mode and a ``degraded H-mode'' with and without good injector synchronization are performed with focus on the first wall heat flux and its energy impact. It is found that low neon fraction SPIs into the baseline H-mode plasmas exhibit strong major radial plasmoid drift as the fragments arrive at the pedestal, accompanied by edge stochasticity. Significant density expulsion and outgoing heat flux occurs as a result, reducing the mitigation efficiency. Such drift motion could be mitigated by injecting higher neon fraction pellets', or by considering the pre-disruption confinement degradation, thus improving the radiation fraction. The radiation heat flux is found to peak in the vicinity of the fragment injection location in the early injection phase, while it relaxes later on due to parallel impurity transport. The overall radiation asymmetry could be significantly mitigated by good synchronization. Time integration of the local heat flux is carried out to provide its energy impact for wall heat damage assessment. For the baseline H-mode case with full pellet injection, melting of the stainless steel armour of the diagnostic port could occur near the injection port, which is acceptable, without any melting of the first wall tungsten tiles. For the degraded H-mode cases with quarter-pellet SPIs, which have 1/4 total volume, the maximum energy impact approaches the tolerable limit of the stainless steel with un-synchronized SPIs, and stays well below such limit for the perfectly synchronized ones.

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Methods to determine the radiated power in SPI-mitigated disruptions in JET

Lovell

Reinke

Sheikh

et al. 2021

Review of Scientific Instruments

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This paper presents techniques for evaluating the radiated power in JET disruptions. Disrupting plasmas are shown to have non-axisymmetric radiation profiles, motivating the re-evaluation of the standard techniques for calculating the total radiated power at JET using bolometry. Four single-channel bolometers at different toroidal locations are exploited to quantify the radiation asymmetry. Toroidal radiation peaking factors integrated over the entire disruption of up to 1.5 have been observed when varying the quantity of neon in pellets used in disruptions mitigated by shattered pellet injection. Using synthetic bolometer diagnostics developed with the Cherab spectroscopy modeling framework, we can estimate the systematic error on total power calculations for relevant radiation profiles and improve estimates of the total radiated power. We show that the component of the systematic error on the total power due to the poloidal radiation profile can be reduced from 70% to 10% with suitable assumptions about the structure of the poloidal profile.

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cherab/core: Release v1.2.0

Cited by 3 publications

References 0 publications

SOLPS-ITER modeling of divertor scenarios for EU-DEMO

SOLPS-ITER modeling of divertor scenarios for EU-DEMO

Plasmoid drift and first wall heat deposition during ITER H-mode dual-SPIs in JOREK simulations

Methods to determine the radiated power in SPI-mitigated disruptions in JET

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