Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments

In the ITER and future fusion devices, W/Cu monoblocks will be used as divertor target which are exposed to both steady state heat load and transient heat flux. Especially, the transient heat flux up to 10 GW m ^−2 during plasma disruption, is expected to induce the shallow surface damages, such as...

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Bibliographic Details

Published in:	Nuclear Fusion
Main Authors:	Zongxiao Guo, Dahuan Zhu, Rong Yan, Chuannan Xuan, Baoguo Wang, Yang Wang, Binfu Gao, Chunyu He, Rui Ding, Yi Li, Wenxue Fu, Junling Chen, the EAST Team
Format:	Article
Language:	English
Published:	IOP Publishing 2024-01-01
Subjects:	W/Cu monoblocks damages transient heat flux heat exhaust capacity EAST ITER
Online Access:	https://doi.org/10.1088/1741-4326/ad4a8b