| 1. |
Chen, X., Zhang, H., Lu, M. et al. Structure optimization and performance analysis of hypervapotron heat exchange channel | [超汽化换热通道结构优化与性能分析]. Nanjing Li Gong Daxue Xuebao/Journal of Nanjing University of Science and Technology, 2025, 49(1): 15-24.
DOI:10.14177/j.cnki.32-1397n.2025.49.01.002
|
|
| 2. |
Wang, X., Li, J., Wang, J.-C. et al. Research on the high heat flux removal technique of a lithium target for the AB-BNCT application. Nuclear Engineering and Technology, 2025.
DOI:10.1016/j.net.2025.103498
|
| 3. |
Yang, X.-K., Yin, L., Yao, D.-M. Design and analysis of the first wall on the NBI shine-through area of high magnetic field side of EAST | [EAST 装置高场侧 NBI 束透区第一壁的设计和分析]. Hejubian Yu Dengliziti Wuli/Nuclear Fusion and Plasma Physics, 2024, 44(4): 451-456.
DOI:10.16568/j.0254-6086.202404012
|
|
| 4. |
Tan, Y., Wang, J., Feng, F. et al. Additive manufacturing of W/RAFM hypervapotron plasma-facing components and the steady state thermal fatigue behavior. Journal of Nuclear Materials, 2024.
DOI:10.1016/j.jnucmat.2024.155333
|
| 5. |
Xuan, C., Zhu, D., Gao, B. et al. Melting of W/Cu flat type component for main limiter and its impact on plasma operation in EAST experiments. Nuclear Fusion, 2024, 64(8): 086039.
DOI:10.1088/1741-4326/ad573e
|
| 6. |
Yao, G., Shen, X., Liu, J.-Q. et al. Study on damage behavior of the outer horizontal target in the EAST lower divertor after plasma operations. Nuclear Materials and Energy, 2024.
DOI:10.1016/j.nme.2024.101640
|
| 7. |
Zhang, X., Wang, Y., Zhong, C. et al. Progress, Load Study, and Structural Analysis of the CFETR Divertor Dome. IEEE Transactions on Plasma Science, 2024, 52(4): 1460-1473.
DOI:10.1109/TPS.2024.3382568
|
| 8. |
Yang, X., Yao, D., Yin, L. et al. Design of the CFC composite brazed HFS first wall on the NBI shine-through area of the EAST device. Fusion Engineering and Design, 2024.
DOI:10.1016/j.fusengdes.2024.114151
|
| 9. |
Lu, M., Han, L., Zhou, J. et al. Thermohydraulic and thermal fatigue characteristics of W/Cu flat-type microchannel mock-up for CFETR divertor. Applied Thermal Engineering, 2024.
DOI:10.1016/j.applthermaleng.2023.122079
|
| 10. |
Xu, T., Cao, L., Peng, X. et al. Design and Research and Development of Front-Face Remote Handling Targets for CFETR Divertor. IEEE Transactions on Plasma Science, 2024, 52(9): 3542-3548.
DOI:10.1109/TPS.2024.3399319
|
| 11. |
Xu, D., Cheng, J., Chen, P. et al. Recent progress in research on bonding technologies of W/Cu monoblocks as the divertor for nuclear fusion reactors. Nuclear Materials and Energy, 2023.
DOI:10.1016/j.nme.2023.101482
|
| 12. |
Zhang, X., Yin, L., Mou, N. et al. Design and thermal-hydraulic analysis for CFETR divertor OVT in consideration of RH compatibility. Fusion Engineering and Design, 2023.
DOI:10.1016/j.fusengdes.2023.113865
|
| 13. |
Liu, C., Zhou, J., Cheng, K. et al. Flow thermohydraulic characterization of open diverging microchannel heat sink for high heat flux dissipation. Applied Thermal Engineering, 2023.
DOI:10.1016/j.applthermaleng.2023.120396
|
| 14. |
Huang, J., Gong, X., Garofalo, A.M. et al. Long-pulse high-performance H-mode plasmas achieved on EAST. Physics of Plasmas, 2023, 30(6): 062504.
DOI:10.1063/5.0146690
|
| 15. |
Zhu, D., Guo, Z., Xuan, C. et al. In situ melting phenomena on W plasma-facing components for lower divertor during long-pulse plasma operations in EAST. Nuclear Fusion, 2023, 63(3): 036022.
DOI:10.1088/1741-4326/acb3e1
|
| 16. |
Ebadi, H., Carrone, F., Difonzo, R. et al. A multi-scale hybrid approach to the modelling and design of a novel micro-channel cooling structure for the W7X divertor. Case Studies in Thermal Engineering, 2023.
DOI:10.1016/j.csite.2023.102734
|
| 17. |
Zhang, X., Xu, T., Yin, L. et al. Front-Face RH Compatible Structure Design and Thermal Analysis for CFETR Divertor Dome. Fusion Science and Technology, 2023, 80(1): 98-107.
DOI:10.1080/15361055.2023.2198482
|
| 18. |
Lu, M., Zhou, J., Chen, X. The Development and Application of Microchannel Heat Sink on W/Cu Flat-Type Mock-Up. IEEE Transactions on Plasma Science, 2022, 50(11): 4213-4219.
DOI:10.1109/TPS.2022.3169809
|
| 19. |
Liu, C., Zhou, J., Zhao, Q. et al. Numerical Investigation of Heat Transfer in Open Microchannel Heat Sinks With Transverse Ribs for High Heat Flux Dissipation. IEEE Transactions on Plasma Science, 2022, 50(11): 4220-4225.
DOI:10.1109/TPS.2022.3167453
|
| 20. |
Lu, M., Han, L., Zhao, Q. et al. Microchannel cooling technique for dissipating high heat flux on W/Cu flat-type mock-up for EAST divertor. Plasma Science and Technology, 2022, 24(9): 095602.
DOI:10.1088/2058-6272/ac684c
|
| 21. |
Zhang, X., Yin, L., Xu, T. et al. Conceptual Design of CFETR Divertor Dome for Remote Handling. IEEE Transactions on Plasma Science, 2022, 50(4): 996-1001.
DOI:10.1109/TPS.2022.3156599
|
| 22. |
Wan, B.N., Gong, X.Z., Liang, Y. et al. Advances in the long-pulse steady-state high beta H-mode scenario with active controls of divertor heat and particle fluxes in EAST. Nuclear Fusion, 2022, 62(4): 042010.
DOI:10.1088/1741-4326/ac2993
|
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