First analysis of in-situ melting on TZM tiles at high field side of the first wall in EAST

Xuan, Chuannan; Zhu, Dahuan; Li, Changjun; Guo, Zongxiao; Gao, Puze; Ding, Rui; Wang, Baoguo; Yu, Baixue; Yang, Lei; Chen, Junling

doi:10.1016/j.nme.2023.101377

Cited by 7 publications

(3 citation statements)

References 17 publications

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“…Budaev, revealing the same three-layer structure under ITERrelevant heat loads especially disruption or ELMs [17]. In our earlier research, this three-layer structure also manifested on PFCs in EAST [19]. It is noteworthy that some cracks in the resolidified layer, along the columnar grain boundaries, are parallel to the heat flux direction.…”

Section: Formation Of a Pre-damaged Surface On W/cu Monoblocks By Tra...supporting

confidence: 61%

“…The molten surface appears notably rough, resembling the wavy surface observed in transient heat tests utilizing electron or ion beams [12]. Additionally, the inconspicuous motion of the molten layer along the vertical direction (the direction of the j × B force) also implies that the molten layer was subjected to an extreme strong plasma stream rather than a steady-state heat load [19]. If it was induced by steady-state heat load, visible downward migration along j × B force of the melting layer, as observed in previous limiters composed of TZM tiles and W/Cu flat-type components [20], should have occurred.…”

Section: Formation Of a Pre-damaged Surface On W/cu Monoblocks By Tra...mentioning

confidence: 92%

“…Although the W/Cu monoblocks of the main limiter in EAST were damaged by transient heat flux, the heat exhaust capacity did not appear to decline significantly due to the damage. Theoretically, the transient heat flux only affects the shallow surface area, causing microscopic changes in the grains [19]. Consequently, the joint interface remains unaffected by transient heat flux, ensuring the continued effectiveness of the heat flux removal channel.…”

Section: Performance Of W/cu Monoblocks With Pre-damaged Surface Unde...mentioning

confidence: 99%

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

Guo,

Zhu,

Yan

et al. 2024

Nucl. Fusion

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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/m2 during plasma disruption, is expected to induce the shallow surface damages, such as melting, and even boiling of W/Cu monoblocks. Thus, the performance of damaged W/Cu monoblocks under subsequent long-term plasma discharges is a key concern that needs to be verified and tested on existing tokamaks. Since 2022, a new type of main limiter composed of ITER-like W/Cu monoblocks has been installed and tested in EAST. The surface of W/Cu monoblocks of the limiter was damaged by the transient heat flux during the early stages of plasma construction. Subsequently, they were subjected to long-term plasma discharges over 2600 shots in normal plasma discharge conditions. This circumstance conveniently facilitates the discussion of the performance of W/Cu monoblocks with damaged surfaces especially a melting edge with hill structure under prolonged exposure to plasma. In general, the shallow damage resulting from transient heat flux on W/Cu monoblocks appears to have minimal impact on the heat exhaust capacity under steady-state heat loads, as indicated by both experimental monitoring and numerical simulation results. However, shallow melting, leading to a change in surface structure and the formation of hills, could theoretically increase local temperatures, creating potential hot spots. This phenomenon requires further validation through dedicated experiments. Moreover, the brittleness of the near-surface layer may give rise to brittle destructions, such as cracks and even dust particles, posing an additional concern. These findings yield unique qualitative conclusions that can be referenced for ITER and other fusion devices.

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Section: Formation Of a Pre-damaged Surface On W/cu Monoblocks By Tra...supporting

confidence: 61%

Section: Formation Of a Pre-damaged Surface On W/cu Monoblocks By Tra...mentioning

confidence: 92%

Section: Performance Of W/cu Monoblocks With Pre-damaged Surface Unde...mentioning

confidence: 99%

See 1 more Smart Citation

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

Guo,

Zhu,

Yan

et al. 2024

Nucl. Fusion

Self Cite

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Simultaneous improvement of strength and plasticity of TZM alloys by introducing α-Al2O3 ceramic particles

Tian,

Xu,

Fang

et al. 2024

Ceramics International

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Damages of TZM as plasma facing material under transient heat load

Yang

Zhu

et al. 2023

Fusion Engineering and Design

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First analysis of in-situ melting on TZM tiles at high field side of the first wall in EAST

Cited by 7 publications

References 17 publications

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

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

Simultaneous improvement of strength and plasticity of TZM alloys by introducing α-Al2O3 ceramic particles

Damages of TZM as plasma facing material under transient heat load

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