Estimation of peak heat flux onto the targets for CFETR with extended divertor leg

Zhang, Chuanjia; Chen, Bin; Xing, Zhe; Wu, Haosheng; Mao, Shaohua; Luo, Z.P.; Peng, Xuebing; Ye, Minyou

doi:10.1016/j.fusengdes.2016.01.009

Cited by 6 publications

(4 citation statements)

References 17 publications

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“…Therefore, developing methods of mitigating the divertor particle and heat load is one of the most crucial issues for the steady-state operation of future reactors such as ITER [3]. Various efforts have been made, such as introducing an advanced magnetic divertor configuration [4][5][6][7], optimizing the divertor geometry [8][9][10][11][12], and exploring an effective scheme of impurity gas seeding [13][14][15][16]. Besides the external methods, the doublepeaked distribution of the particle deposition onto the divertor target, which is formed due to the intrinsic transport process in the scrape-off layer (SOL), has been recently considered as a potential approach for mitigating the divertor particle flux and heat load [17].…”

Section: Introductionmentioning

confidence: 99%

Simulation study of the influence of upstream density and power in the scrape-off layer on the double-peaked density profile at the divertor target

Guo¹,

Mao²,

Jia³

et al. 2022

Nucl. Fusion

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The double-peaked distribution of particle deposition at the divertor targets has been observed in various tokamaks, and is considered as a potential approach for mitigating the divertor particle and heat load in future fusion reactor. Recently, the systematical analysis of the double-peaked distribution behavior during EAST experiments show that, the appearance of the double-peaked profile is related to the line-average density and heating power. In order to understand the general trends and related mechanisms, the influences of the upstream density (ne,sep) and power into scrape-off layer (PSOL) on the double-peaked density profile are investigated by SOLPS-ITER simulations with full drifts and currents. It is found that, the ne peak near the strike point is mainly contributed by the strong ionization source close to the target, and the ne peak in far-SOL region is caused by the synergetic effects of poloidal and radial E×B drifts along the SOL. The double-peaked distribution is affected by the PSOL and impurity seeding by increasing or decrease the whole profile of the electron temperature at the target (Tet). When the peak value of Tet (Tet,peak) is fixed, the density peak in the far-SOL is increased for higher ne,sep, by reducing the Tet in the far-SOL region on the lower-field side under unfavorable BT, and by the upstream-extended ionization source due to the geometry effect on the high-field side under favorable BT. Statistical analysis of the simulated results shows that the scaling expression of the peak ratio is ~Tet,peak -(1.4~2.1) ne,sep 1.6~1.8. In addition to upper boundary found in the analysis of EAST experiment, a lower boundary of the region where double-peaked feature appears on the PSOL-ne,sep plane is identified by simulations and preliminarily confirmed according to the measurements in several EAST discharges.

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Section: Introductionmentioning

confidence: 99%

Simulation study of the influence of upstream density and power in the scrape-off layer on the double-peaked density profile at the divertor target

Guo¹,

Mao²,

Jia³

et al. 2022

Nucl. Fusion

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“…The distance between the first separatrix and the second separatrix, ∆R sep , is 6 cm at the outer mid-plane (OMP). Several divertor design schemes have been proposed and studied, including conventional [21], snowflake [22], and long-leg divertors [23]. In our modelling work, a conventional divertor with vertical target plates is used, which is consistent with the CFETR divertor design [21].…”

Section: Methodsmentioning

confidence: 99%

Modelling of the complete heat flux deposition on the CFETR first wall with neon seeding

Nian

Yang

Ding

et al. 2021

Plasma Phys. Control. Fusion

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Steady-state heat flux deposition on the first wall of the Chinese Fusion Engineering Testing Reactor (CFETR) is investigated for 1 GW fusion power and under the updated design scheme. The computation is accomplished by the modelling of two simulation systems: SOLPS-ITER and PFCFlux. Seeding neon (Ne) gas is considered to be one of the possible methods of protecting the CFETR divertor from high heat flux damage. Simulations with different Ne seeding rates were carried out on a standard divertor with a lower single-null configuration to determine the effect of Ne seeding on heat flux deposition on the first wall. A blob-based transport model was used to investigate the effect of enhanced cross-field transport on the CFETR first wall, as with ITER and EU DEMO simulations. This work establishes a potential method for simulating the complete heat flux deposition on the first wall for the CFETR steady state by SOLPS-ITER and PFCFlux. After modelling and energy analysis, the peak value of complete heat flux on each module of the CFETR first wall is obtained, which may provide the basic reference for the CFETR physics and engineering design team. The CFETR first wall module which receives the highest heat flux has also been identified, and Ne seeding has a positive effect on reducing the heat flux on the CFETR first wall from around 2.5 MW m −2 to 1 MW m −2 , which is within the engineering requirement.

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“…SOLPS is a boundary plasma code composed of two coupled codes, i.e. B2.5 (a multi-fluid code for plasma transport calculation) and EIRENE (a Monte-Carlo code for neutral transport calculation) [55], and widely applied to many tokamaks to study the divertor physics and boundary plasma transport [8,10,39,[56][57][58][59][60][61][62][63][64][65][66][67][68][69]. The latest version SOLPS-ITER introduces advanced models for the drift effect and neutral transport [70] and has been recognized as an effective tool for studying the effect of drift on the SOL plasma [42,43,45].…”

Section: Simulation Schemementioning

confidence: 99%

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

Guo,

Xu,

Mao

et al. 2023

Nucl. Fusion

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Future fusion reactors such as ITER have adopted tungsten (W) as the plasma-facing materials (PFMs) in the divertor region. It is crucial to keep the W concentration in the core plasma at an extremely low level. Great efforts have been put forward on understanding the W transport in the scrape-off layer (SOL), which is related to the source of the core W contamination. In this work, the influence of E×B drift on the W impurity transport in the SOL is studied by numerical simulations for a model case based on EAST upper single-null configuration with high recycling divertor plasma. The W transport is simulated using DIVIMP on the background plasma obtained from SOLPS-ITER simulation including drifts. The E×B drift of the W ions is introduced according to the background electric field. Therefore, both the direct E×B drift effect of W ion itself and the indirect effect via background plasma on the W transport process in the SOL can be studied. We focus on the influence on the flux of W impurities entering confined plasma across the last closed flux surface Γenter, which is expected to be proportional to the core W concentration. It is found that Γenter is mainly from the outer (inner) target under favorable (unfavorable) toroidal field BT, and can be increased by more than one order of magnitude compared with the case without drifts. It reflects the significant influence of E×B drift effects. The detailed effects due to the background plasma and the poloidal and radial E×B drift of W ion, as well as the related mechanisms, are analyzed for the three stages of W transport in the SOL, including the effective sputtering from the target, the leakage from the divertor and the entry into the confined plasma.

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Estimation of peak heat flux onto the targets for CFETR with extended divertor leg

Cited by 6 publications

References 17 publications

Simulation study of the influence of upstream density and power in the scrape-off layer on the double-peaked density profile at the divertor target

Simulation study of the influence of upstream density and power in the scrape-off layer on the double-peaked density profile at the divertor target

Modelling of the complete heat flux deposition on the CFETR first wall with neon seeding

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

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