Cfetr Physics Team
University of Science and Technology of China
15 Papers
36 Citations
Cfetr Physics Team is an academic researcher from University of Science and Technology of China. The author has contributed to research in topics: Tokamak & Fusion power. The author has an hindex of 6, co-authored 14 publications.
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Papers
Overview of the present progress and activities on the CFETR
Yuanxi Wan,Yuanxi Wan,Jiangang Li,Yong Liu,Xiaolin Wang,Vincent Chan,Chang’an Chen,Xuru Duan,P. Fu,Xiang Gao,Kaiming Feng,Liu Songlin,Yuntao Song,Peide Weng,Baonian Wan,Farong Wan,Heyi Wang,Songtao Wu,Minyou Ye,Qingwei Yang,G.Y. Zheng,Ge Zhuang,Qiang Li,Cfetr Physics Team +23 more
TL;DR: The China Fusion Engineering Test Reactor (CFETR) is the next device in the roadmap for the realization of fusion energy in China, which aims to bridge the gaps between the fusion experimental reactor ITER and the demonstration reactor (DEMO).
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Evaluating the effects of tungsten on CFETR phase I performance
Shengyu Shi,Shengyu Shi,Xiang Jian,Xiang Jian,Vincent Chan,Vincent Chan,Xiang Gao,Xiaoju Liu,Nan Shi,Jiale Chen,Li Liu,M. Q. Wu,Yi-Ren Zhu,Cfetr Physics Team +13 more
Abstract: An integrated modeling workflow using OMFIT is constructed to evaluate the effects of tungsten (W) impurity on China Fusion Engineering Test Reactor (CFETR) performance. Self-consistent modeling of W core density profile, accounting for both turbulent and neoclassical transport contributions, is performed based on the steady-state scenario of CFETR phase I (Wan et al 2016 IAEA; Wan et al 2017 Nucl. Fusion 57 102009). It is found that the fusion performance degrades mildly with increasing W concentration. The main challenge arises in the sustainment of H-mode operation with significant W radiation. Assuming that the power threshold of H–L back transition is approximately the same as that of L–H transition, the W fraction at the plasma boundary is not allowed to exceed to stay in H-mode for CFETR phase I according to the scaling law proposed by Takizuka et al (2004 Plasma Phys. Control Fusion 46 A227–33). In addition, the tolerance of W concentration decreases with increasing pedestal density through a trade-off study of pedestal density and temperature. A future step is to connect the core simulation to W wall erosion modeling.
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SOLPS-ITER modeling of CFETR advanced divertor with Ar and Ne seeding
I. Senichenkov,R. Jeff Ding,P. Molchanov,E. G. Kaveeva,V. A. Rozhansky,S. P. Voskoboynikov,N. V. Shtyrkhunov,Sergey N. Makarov,H. Si,X. Liu,Chaofeng Sang,Shifeng Mao,Cfetr Physics Team +12 more
TL;DR: In this paper , the results of the CFETR advanced divertor optimization by SOLPS-ITER modeling with full drifts and currents activated are presented and three divertor geometries, which differ by the distance from the X-point to the strike point on the outer target, are considered.
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Edge localized mode characteristics and divertor heat flux during stationary and transient phase for CFETR hybrid scenario
Zeyu Li,Zeyu Li,Yi-Ren Zhu,Guoliang Xu,Vincent Chan,Vincent Chan,Xueqiao Xu,Jiale Chen,Rui Ding,T.Y. Xia,Xiang Jian,Yunpeng Zou,Chijie Xiao,Xiaogang Wang,Xiaogang Wang,Cfetr Physics Team +15 more
TL;DR: In this paper, the impact of transient peak heat load and ELM energy fluence on tungsten melting and net erosion rate of divertor target was evaluated for the first-time using physics-based transport that connects the pedestal with the scrape-off-layer.
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