Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET

Kumpulainen, H.; Groth, M.; Corrigan, G.; Harting, D.; Koechl, F.; Jaervinen, A.E.; Lomanowski, B.; Meigs, A.; Sertoli, M.; Contributors, Jet

doi:10.1016/j.nme.2020.100866

Cited by 11 publications

(10 citation statements)

References 13 publications

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“…However, the W II emission is simultaneously underpredicted by one order of magnitude, which calls for further investigations of assumptions affecting the W 1+ species in ERO2.0. This is in contrast to earlier work [5], using JINTRAC to predict the W erosion, which reported the opposite discrepancy of overpredicting the W II emission due to the lack of a prompt redeposition model in JINTRAC.…”

Section: Discussioncontrasting

confidence: 99%

“…The aim of this study is to extend earlier modelling of W sources in JET plasmas [2][3][4][5][6][7] to higher-performance scenarios with large type-I edge-localised modes (ELMs), with an emphasis on the validation of the simulated plasma conditions and the plasma-surface interaction models. This is a critical step on the path to validating edge and core plasma impurity transport predictions, as it provides a means to distinguish between uncertainties due to the impurity sources and due to the transport model.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

Kumpulainen

Groth²,

Brezinsek³

et al. 2022

Nuclear Materials and Energy

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Section: Discussioncontrasting

confidence: 99%

Section: Introductionmentioning

confidence: 99%

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

Kumpulainen

Groth²,

Brezinsek³

et al. 2022

Nuclear Materials and Energy

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“…Divertor screening of W in the more open magnetic configuration (S-P on the horizontal divertor plates) is ∼1.7 higher than that with S-P at the far corner, near the pumping duct entrance. Modelling of W transport in JET SOL with EDGE2D-EIRENE and DIVIMP [81] shows that accurate predictions of W density needs a good match to the experimental pedestal and SOL, and that incidence angle, surface roughness, material mix, and W prompt re-deposition must be taken into account to reproduce the measured W I, W II emission. The modelling suggests that sputtering by energetic CX fuel atoms near the top of the outer vertical divertor (where divertor screening does not apply) could contribute significantly to the W influx in the confined plasma in L-mode and inter-ELM phases.…”

Section: W and Be Erosion Transport And Screeningmentioning

confidence: 99%

Overview of JET results for optimising ITER operation

et al. 2022

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The JET 2019-2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major Neutral Beam Injection (NBI) upgrade providing record power in 2019-2020, and tested the technical & procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle physics in the coming D-T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed Shattered Pellet Injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design & operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D-T benefited from the highest D-D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER.

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“…Impurities that reach the innermost core boundary are reflected, while those that impinge upon the divertor target or outermost edge of the grid are removed. DIVIMP includes all the forces in equation ( 1), as well as the inertia of the particles (consider the kinetic/fluid comparisons of W transport in [9,40]). The effect of ELMs on impurity transport is not explicitly considered in DIVIMP, though the specified anomalous diffusion coefficient may be considered as including the time-averaged contribution of ELMs to the impurity radial transport.…”

Section: Divimp: Injection Of Impurities and The Effect Of Fast Paral...mentioning

confidence: 99%

“…Recent studies have nevertheless made significant advances in understanding edge impurity transport despite sometimes having little to no experimental measurements of impurity ion density along the separatrix between the X-points. Insights into the key drivers behind the poloidal structure of impurity ions have been obtained in SOLPS [5] modeling comparing the magnitude of leakage between different injected impurities on ASDEX-U [6], also in DIVIMP simulations of expected W distributions for the DIII-D metal rings campaign (MRC) [7], as well as EDGE2D-EIRENE/DIVIMP [8] code comparison studies of radial W profiles on JET [9].…”

Section: Introductionmentioning

confidence: 99%

The role of B _T-dependent flows on W accumulation at the edge of the confined plasma

et al. 2022

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Near-separatrix impurity accumulation between the crown and the outer midplane of tokamaks is a common feature in results from codes such as SOLPS-ITER and DIVIMP; however, experimental evidence of accumulation has only recently been obtained and is reported here. The codes find that the poloidal distribution of impurity ions in the scrape-off layer (SOL) depends primarily on toroidal field (BT)-dependent parallel flow patterns of the background plasma and the parallel ion temperature gradient (∇||Tion) force. Experimentally, Mach probes used in L-mode plasmas with favorable (for H-mode access) BT measure fast (M~0.3-0.5) inner-target-directed (ITD) background plasma flows at the crown of single-null discharges. This study reports a set of DIVIMP simulations for two similar H-mode discharges from the DIII-D W Metal Rings Campaign differing primarily in BT-direction to assess the effect that fast ITD flows have on the distribution of W ions in the SOL. It is found that for imposed ITD flows of M = 0.3, W ions that otherwise accumulate due to the ∇||Tion-force are largely flushed out. It is also found that doubling the radial diffusion coefficient from 0.3 to 0.6 m2/s prevents accumulation due to rapid cross-field transport into the far-SOL, where background plasma flows drain W ions to the divertors. Far-SOL W distributions from DIVIMP are then used to specify input to the impurity transport code 3DLIM, which is used to interpretively model collector probe deposition patterns measured in the “wall-SOL.” It is demonstrated that the deposition patterns are consistent with the DIVIMP predictions of near-SOL accumulation for the unfavorable-BT direction, and little/no accumulation for the favorable-BT direction. The wall-SOL collector probes have thus provided the first experimental evidence, albeit indirect, of near-SOL W accumulation – finding it occurs for the unfavorable-BT direction only. For the favorable-BT direction, fast flows can largely prevent accumulation from occurring.

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Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET

Cited by 11 publications

References 13 publications

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

Overview of JET results for optimising ITER operation

The role of B _T-dependent flows on W accumulation at the edge of the confined plasma

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Validation of EDGE2D-EIRENE and DIVIMP for W SOL transport in JET

Cited by 11 publications

References 13 publications

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

ELM and inter-ELM tungsten erosion sources in high-power, JET ITER-like wall H-mode plasmas

Overview of JET results for optimising ITER operation

The role of B T-dependent flows on W accumulation at the edge of the confined plasma

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The role of B _T-dependent flows on W accumulation at the edge of the confined plasma