Toroidal distribution of heat load on castellated plasma facing components for lower divertor target in EAST

作者：Wenxue Fu, Dahuan Zhu, Binfu Gao, Zongxiao Guo, Bin Zhang, M. Firdaouss, Chuannan Xuan, Rong Yan, Yang Wang, Chunyu He, Yi Li, Baoguo Wang, Rui Ding, Junling Chen · 发表于：Nuclear Materials and Energy · 年份：2024 · DOI：10.1016/j.nme.2024.101759 · 被引用次数：3 · 研究领域：Magnetic confinement fusion research、Fusion materials and technologies、Laser-Plasma Interactions and Diagnostics

• The heat load on the target surface in EAST exhibits significant toroidal non-uniformity, with the heat deposition and temperature pattern being generally consistent and showing periodic variations. • The toroidal distribution of heat load is stongly related to the configuration of magnetic field and structure of plasma facing component. In tokamak devices, the performance of plasma facing components (PFCs) under high heat loads is a key challenge for achieving long-pulse and high-performance plasma operations. The lower divertor of EAST adopts an ITER-like cassette modules (CMs) structure. However, regular distribution of damage along the toroidal direction have been observed on the divertor target plates, which not only affects the lifespan of PFCs but also limits the long-pulse and high-performance plasma operations. Therefore, investigating the toroidal distribution of the heat load on the divertor target in EAST is crucial for understanding the mechanism of damage on the target plate surface. The toroidal characteristics of heat loads on CMs of the lower divertor in EAST was analyzed using a three-dimensional magnetic field line tracing program (PFCFlux). For the inner vertical target (IVT) and outer vertical target (OVT) within a single CM, the heat load varies monotonically along the toroidal direction. In contrast, the heat load distribution on the outer horizontal target (OHT) is uniform, except at the chamfers, which is directly correlated with the target’s geomet...