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Impact of W monoblock damage on EAST operations in recent campaigns
Fusion engineering and design, 2021-08, Vol.169, p.112623, Article 112623
2021
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Characterization on the melting failure of CuCrZr cooling tube of W/Cu monoblocks during plasma operations in EAST
Nuclear materials and energy, 2020-12, Vol.25, p.100847, Article 100847
2020
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Interface cracking damage of W/Cu monoblocks as divertor target after high-cyclic plasma discharges in EAST
Nuclear materials and energy, 2024-06, Vol.39, p.101665, Article 101665
2024
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First analysis of in-situ melting on TZM tiles at high field side of the first wall in EAST
Nuclear materials and energy, 2023-03, Vol.34, p.101377, Article 101377
2023
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Observations on arcing on the metal plasma-facing components in EAST
Nuclear materials and energy, 2023-03, Vol.34, p.101318, Article 101318
2023
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Experiences and lessons from the mitigation of leading edge induced melting on actively cooled ITER-like W/Cu monoblocks for divertor target in EAST
Nuclear materials and energy, 2023-12, Vol.37, p.101524, Article 101524
2023
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Result and discussion on the evolution of in-situ leading edge-induced melting on W divertor targets in EAST
Nuclear materials and energy, 2021-06, Vol.27, p.100997, Article 100997
2021
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Analysis of the transient heat flux on divertor surface during plasma disruption in EAST
Nuclear materials and energy, 2023-09, Vol.36, p.101503, Article 101503
2023
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Characterization of the peak temperature on upper W divertor target during D and He plasma discharges in EAST
Nuclear materials and energy, 2023-03, Vol.34, p.101362, Article 101362
2023
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Studies of material deposition on the graphite divertor tile after the 2019 experimental campaign in EAST
Nuclear materials and energy, 2022-10, Vol.33, p.101252, Article 101252
2022
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Studies of material migration and deposition after the 2017 experimental campaign in EAST
Nuclear materials and energy, 2022-03, Vol.30, p.101103, Article 101103
2022
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Melting of W/Cu flat type component for main limiter and its impact on plasma operation in EAST experiments
Nuclear fusion, 2024-08, Vol.64 (8), p.86039
2024
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Plasma-facing components damage and its effects on plasma performance in EAST tokamak
Fusion engineering and design, 2020-07, Vol.156, p.111616, Article 111616
2020
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Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments
Nuclear fusion, 2024-07, Vol.64 (7), p.76026
2024
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Optimization of the chamfering structures for ITER-like W/Cu monoblocks to avoid the leading edge-induced melting in EAST
Fusion engineering and design, 2020-12, Vol.161, p.111951, Article 111951
2020
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Characterization of SOL profiles and turbulence in ICRF-heated plasmas in EAST
Nuclear fusion, 2024-05, Vol.64 (5), p.56023
2024
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Evidence of vapor shielding effect on heat flux loaded on flowing liquid lithium limiter in EAST
Plasma science & technology, 2022-09, Vol.24 (9), p.95104
2022
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High exogenous humus inhibits greenhouse gas emissions from steppe lakes
Environmental pollution (1987), 2023-02, Vol.319, p.120946-120946, Article 120946
2023
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