Experimental investigation on divertor tungsten sputtering with neon seeding in ELMy H-mode plasma in EAST tokamak

Ye, Dawei; Ding, Fang; Li, Kedong; Hu, Zhenhua; Zhang, Ling; Chen, Xiaohua; Zhang, Qin; Zhao, Pingan; He, Tao; Meng, Lingyi; Ye, Kaixuan; Zhong, Fubin; Duan, Yanmin; Ding, Rui; Wang, Liang; Xu, G. S.; Luo, Guang–Nan; Team, the EAST

doi:10.1088/1674-1056/ac4f58

Cited by 5 publications

(1 citation statement)

References 25 publications

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“…In forward B t cases, a similar trend of integrated OT Γ ERO W with T peak e,OT is also observed, see figure 12(d). This is due to the fact that inadequate seeded impurities can give rise to larger Γ ERO W depending on the competition between lower T e and increased incident Ne ion flux [4], which is in accordance with the measurement of sputtered W flux during the Ne seeding experiment on EAST [29]. However, larger Γ ERO W does not necessarily raise C CEI W (figures 12(a) and (c)) since the divertor regime also plays an important role in W accumulation in the core, which was demonstrated by our previous work [3] and DIVIMP simulations on EAST [22].…”

Section: Influence Of Ne Puffing Rate On W Transport and Accumulation...supporting

confidence: 85%

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

et al. 2023

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Mitigating tungsten (W) wall erosion and core accumulation is vitally important to the steady-state operation of tokamaks. It is well known that drifts have a great impact on the transport of charged particles in the edge region, which could affect W source and W impurity transport. In this work, SOLPS-ITER modeling is applied to study the W impurity behavior on EAST during neon seeding with the consideration of E×B drift. The objective is to find out the relationship between the eroded W flux, W transport and corresponding accumulation in core in different discharge regimes. The effect of drift on W sputtering at targets and W impurity distribution in the cases of different toroidal magnetic field (Bt) directions is assessed. The simulation results indicate that drift could influence W transport via W impurity retention and redistribution in divertor, and the leakage from divertor. In forward Bt (B×∇B points to the X-point), eroded W flux at outer target is increased remarkably, and most of the W ions transport from outer to inner divertor and escape to upstream region in high field side. While W ions mainly transport from inner to outer divertor and escape from divertor in low field side in reversed Bt due to the opposite drift flux. Ne puffing rate is scanned in forward Bt and without drift cases to further investigate the W erosion and W impurity transport in different divertor regimes. It is found that W source from targets is generally enhanced by drift compared to the without drift cases. The core accumulation as well as poloidal asymmetry is also influenced significantly by the drift. In attached regime, intense W source and strong drift flux lead to enhanced W accumulation in the core, and obvious poloidal asymmetry of W density distribution appears. The drift flux is reduced, and W erosion is suppressed after detachment. W concentration in the core and poloidal asymmetry declines consequently. Therefore, adequate Ne impurity seeding can be applied to control the W accumulation in the core.

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Section: Influence Of Ne Puffing Rate On W Transport and Accumulation...supporting

confidence: 85%

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

et al. 2023

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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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Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

Parsons,

Mateja,

Messer

et al. 2023

Nuclear Materials and Energy

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Experimental investigation on divertor tungsten sputtering with neon seeding in ELMy H-mode plasma in EAST tokamak

Cited by 5 publications

References 25 publications

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

All superconducting tokamak: EAST

Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

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