Characterization of in situ damage to tungsten PFCs induced by transient heat flux during plasma disruption in EAST

Transient heat flux of up to several thousand MW m ^−2 in a short pulse (∼ms) in tokamaks poses great risk to plasma-facing components (PFCs), making it a major concern for ITER. Despite numerous high heat flux tests, analysis of in situ transient heat flux-induced damage to PFCs remains necessary....

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Bibliographic Details
Main Authors: Chuannan Xuan, Dahuan Zhu, Yang Wang, Binfu Gao, Wenxue Fu, Zongxiao Guo, Rui Ding, Baoguo Wang, Pengfei Zi, Junling Chen, the EAST Team
Format: Article
Language:English
Published: IOP Publishing 2025-01-01
Series:Nuclear Fusion
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Online Access:https://doi.org/10.1088/1741-4326/adc1e0
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