Understanding core heavy impurity transport in a hybrid discharge on EAST

Shi, Shengyu; Chen, Jiale; Bourdelle, C.; Xiang, Jian; Odstrčil, T.; Garofalo, A. M.; Cheng, Yunxin; Yan, Chen; Zhang, Ling; Duan, Yanmin; Wu, Mingfu; Ding, Fang; Qian, J.; Gao, Xiang

doi:10.1088/1741-4326/ac3e3b

Cited by 14 publications

(18 citation statements)

References 77 publications

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“…The maximum density of W (1)(2)(3)(4)(5)(6)(7)(8)(9)(10)+ ions near the target plates is more than 1.0 × 10 16 m −3 in figure 3(a). The W (11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(23)(24)(25)(26)(27)(28)+ ions can penetrate into the LCFS due to the higher ionization potential. Particularly, the W (11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(23)(24)(25)(26)(27)(28)+ ions density (as well as energy loss as later shown in figure 3(d)) is obviously higher at the inboard divertor than the outboard divertor, which will be studied in detail below.…”

Section: The Transport Behaviors Of W Impurity In the Edge Regionmentioning

confidence: 99%

“…The W (11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(23)(24)(25)(26)(27)(28)+ ions can penetrate into the LCFS due to the higher ionization potential. Particularly, the W (11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(23)(24)(25)(26)(27)(28)+ ions density (as well as energy loss as later shown in figure 3(d)) is obviously higher at the inboard divertor than the outboard divertor, which will be studied in detail below. In addition, the W ions with higher charge states (W (29-74)+ ) are mainly distributed in the core region, which is beyond the scope of EMC3-EIRENE simulation domain and will be studied by STRAHL modelling in section 3.3.…”

Section: The Transport Behaviors Of W Impurity In the Edge Regionmentioning

confidence: 99%

“…The energy losses caused by W (1-10)+ and W (11)(12)(13)(14)(15)(16)(17)(18)(19)(20)(21)(22)(23)(24)(25)(26)(27)(28)+ ions are shown in figures 3(c) and (d). The energy loss caused by W (1-10)+ mainly concentrates near the strike points and in the PFR, which has a high W (1)(2)(3)(4)(5)(6)(7)(8)(9)(10)+ ions density (in figure 3(a)).…”

Section: The Transport Behaviors Of W Impurity In the Edge Regionmentioning

confidence: 99%

“…Additionally, the poloidal asymmetry of the core W impurity has been studied with GKW/NEO codes on AUG and JET [24]. Moreover, TGYRO/STRAHL modelling is employed to investigate the W core accumulation on EAST under high normalized beta β N scenarios [28].…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL

Liu¹,

Dai²,

Yang³

et al. 2022

Nucl. Fusion

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The edge transport and core accumulation of tungsten (W) particles on CFETR have been studied by integrated modelling consisting of EMC3-EIRENE and STRAHL codes. The edge transport and power dissipation of W particles are simulated by EMC3-EIRENE. An in-out asymmetry of W(1-28)+ ions density has been revealed in the in- and out-board divertor regions. This is mainly due to the stronger reversal flow velocity of W ions at the outboard divertor. The upward flow of W ions near the separatrix leads to a moderate W impurity leakage from the divertor on CFETR compared to the existing full W device ASDEX Upgrade due to the high plasma density near the CFETR divertor targets. Further, the density distribution and radiation loss of W ions in the core region are investigated by STRAHL code. The high charge-state W(29-60)+ and W(61-74)+ ions mainly reside in the regions of Ψ_N = 0.20~0.98 and 0.00~0.90 (Ψ_N is the normalized poloidal magnetic flux), respectively. The W induced energy dissipation in different regions is assessed according to both STRAHL and EMC3-EIRENE simulations. Particularly, the impacts of the W core radiation on the operation regime are discussed according to the H-mode threshold scaling law proposed by Martin [Martin Y R et al 2008 J. Phys.: Conf. Ser. 123 012033] for the baseline plasma on CFETR. Further, parameter studies on the pinch velocity (v_imp) and diffusion coefficient (D_imp) have been performed to check their impacts on the operation regime of CFETR. A three-fold increase of v_imp/D_imp results in a higher W core energy loss, which can lead to the transition from H-mode back to L-mode.

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Section: The Transport Behaviors Of W Impurity In the Edge Regionmentioning

confidence: 99%

Section: The Transport Behaviors Of W Impurity In the Edge Regionmentioning

confidence: 99%

Section: The Transport Behaviors Of W Impurity In the Edge Regionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL

Liu¹,

Dai²,

Yang³

et al. 2022

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

“…Recent developments in integrated modelling have been dedicated to the description of impurity transport [17][18][19][20][21][22][23][24], including the evolution of the background plasma with radiative losses by impurities [25][26][27]. However, some limitations are present either because the boundary condition is set well inside the confined plasma, or because empirical impurity transport coefficients are used at the edge.…”

Section: Introductionmentioning

confidence: 99%

Full-radius integrated modelling of ASDEX Upgrade L-modes including impurity transport and radiation

Fajardo,

Angioni,

Dux

et al. 2024

Nucl. Fusion

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An integrated framework that demonstrates multi-species, multi-channel modelling capabilities for the prediction of impurity density profiles and their feedback on the main plasma through radiative cooling and fuel dilution is presented. It combines all presently known theoretical elements in the local description of quasilinear turbulent and neoclassical impurity transport, using the models TGLF-SAT2 and FACIT. These are coupled to the STRAHL code for impurity sources and radiation inside the ASTRA transport solver. The workflow is shown to reproduce experimental results in full-radius L-mode modelling. In particular, a set of ASDEX Upgrade L-modes with differing heating power mixtures and plasma currents are simulated, including boron (B) and tungsten (W) as intrinsic impurities. The increase of predicted confinement with higher current and the reduction of core W peaking with higher central wave heating are demonstrated. Furthermore, a highly radiative L-mode scenario featuring an X-point radiator (XPR) with two intrinsic (B, W) and one seeded argon (Ar) species is simulated, and its measured radiated power and high confinement are recovered by the modelling. The stabilizing effect of impurities on turbulence is analyzed and a simple model for the peripheral X-point radiation is introduced. A preliminary full-radius simulation of an H-mode phase of this same discharge, leveraging recent work on the role of the E×B shearing at the edge, shows promising results.

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All superconducting tokamak: EAST

Wang

Zhang

et al. 2023

AAPPS Bull.

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Experimental Advanced Superconducting Tokamak (EAST) was built to demonstrate high-power, long-pulse operations under fusion-relevant conditions, with major radius R = 1.9 m, minor radius a = 0.5 m, and design pulse length up to 1000s. It has an ITER-like D-shaped cross-section with two symmetric divertors at the top and bottom, accommodating both single null and double null divertor configurations. EAST construction was started in 2000, and its first plasma was successfully obtained in 2006. In the past 15 years, plasma-facing components, plasma heating, diagnostics, and other systems have been upgraded step by step to meet its mission on exploring of the scientific and technological bases for fusion reactors and studying the physics and engineering technology issues with long pulse steady-state operation. An advanced steady-state plasma operation scenario has been developed, and plasma parameters were greatly improved. Meanwhile, front physics on the magnetic confinement plasmas have been systemically investigated and lots of fruitful results were realized, covering transport and confinement, MHD stabilities, pedestal physics, divertor and scrap-off layer (SOL) physics, and energetic particle physics. This brief review of EAST on engineering upgrading, stand-steady operation scenario development, and plasma physics investigation would be useful for the reference on construction and operation of a superconducting tokamak, such as ITER and future fusion reactor.

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Understanding core heavy impurity transport in a hybrid discharge on EAST

Cited by 14 publications

References 77 publications

Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL

Evaluation of edge transport and core accumulation of tungsten for CFETR with EMC3-EIRENE and STRAHL

Full-radius integrated modelling of ASDEX Upgrade L-modes including impurity transport and radiation

All superconducting tokamak: EAST

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