| Simulations of tokamak boundary plasma turbulence transport in setting the divertor heat flux width XQ Xu, NM Li, ZY Li, B Chen, TY Xia, TF Tang, B Zhu, VS Chan Nuclear Fusion 59 (12), 126039, 2019 | 61 | 2019 |
| Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module ZY Li, XQ Xu, NM Li, VS Chan, XG Wang Nuclear Fusion 59 (4), 046014, 2019 | 50 | 2019 |
| Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths B Chen, XQ Xu, TY Xia, NM Li, M Porkolab, E Edlund, B LaBombard, ... Physics of Plasmas 25 (5), 2018 | 21 | 2018 |
| Calculation of two-dimension radial electric field in boundary plasmas by using BOUT++ NM Li, XQ Xu, TD Rognlien, B Gui, JZ Sun, DZ Wang Computer Physics Communications 228, 69-82, 2018 | 19 | 2018 |
| Impact of plasma density/collisionality on divertor heat flux width NM Li, XQ Xu, RJ Goldston, JZ Sun, DZ Wang Nuclear Fusion 61 (2), 026005, 2020 | 17 | 2020 |
| Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework NM Li, XQ Xu, JW Hughes, JL Terry, JZ Sun, DZ Wang AIP Advances 10 (1), 2020 | 15 | 2020 |
| Simulation of divertor heat flux width on EAST by BOUT++ transport code GZ Deng, XQ Xu, NM Li, XJ Liu, X Liu, JC Xu, W Feng, JB Liu, SL Gao, ... Nuclear Fusion 60 (8), 082007, 2020 | 11 | 2020 |
| Effects of radial transport on divertor power and particle flux widths under different operational regimes in EAST GZ Deng, XQ Xu, XJ Liu, JC Xu, LY Meng, JB Liu, NM Li, L Schmitz, ... Nuclear Fusion 61 (10), 106015, 2021 | 8 | 2021 |
| Data-driven model for divertor plasma detachment prediction B Zhu, M Zhao, H Bhatia, X Xu, PT Bremer, W Meyer, N Li, T Rognlien Journal of Plasma Physics 88 (5), 895880504, 2022 | 7 | 2022 |
| Characteristics of grassy ELMs and their impact on the divertor heat flux width N Li, XQ Xu, YF Wang, N Yan, JY Zhang, JP Qian, JZ Sun, DZ Wang Nuclear Fusion 62 (9), 096030, 2022 | 7 | 2022 |
| Numerical simulation of Li pellet ablation in the H-mode pedestal region J Sun, L Liu, Z Sun, M Li, N Li, D Wang Fusion Engineering and Design 136, 834-838, 2018 | 7 | 2018 |
| Numerical investigation on lithium transport in the edge plasma of EAST real-time-Li-injection experiments in the frame of BOUT++ NM Li, JZ Sun, ZH Wang, XQ Xu, Z Sun, L Wang, JS Hu, DZ Wang Nuclear Materials and Energy 12, 119-123, 2017 | 6 | 2017 |
| Small-ELM-regime access facilitated by new tungsten divertor on EAST GS Xu, X Lin, QQ Yang, YF Wang, GZ Jia, NM Li, N Yan, R Chen, XQ Xu, ... 48th EPS Conference on Plasma Physics, 2022 | 4 | 2022 |
| How fluctuation intensity flux drives SOL expansion N Li, XQ Xu, PH Diamond, T Zhang, X Liu, YF Wang, N Yan, GS Xu Nuclear Fusion 63 (LLNL-JRNL-845666), 2023 | 3 | 2023 |
| Impact of pedestal density gradient and collisionality on ELM dynamics N Li, XQ Xu, YF Wang, X Lin, N Yan, GS Xu Physics of Plasmas 29 (12), 2022 | 3 | 2022 |
| Modeling of small tungsten dust grains in EAST tokamak with NDS-BOUT++ Z Liu, R Ding, X Xu, N Li, G Deng, J Sun, D Wang, Y Feng Physics of Plasmas 28 (12), 2021 | 3 | 2021 |
| Simulation of plasma transport in MPS-LD linear plasma device by using BOUT++ Y Wang, C Sang, N Li, Y Huang, Y Zhang, C Sun, Y Bian, A Zhu, D Wang Plasma Physics and Controlled Fusion 64 (11), 115010, 2022 | 2 | 2022 |
| Corrigendum: Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module (2019 Nucl. Fusion 59 046014) Z Li, X Xu, NM Li, VS Chan, XG Wang Nuclear Fusion 60 (2), 029502, 2020 | 2 | 2020 |
| Effect of divertor plasma-facing materials and drift on the power decay width in the scrape-off layer and divertor on EAST C Zhang, C Sang, L Wang, Y Zhang, N Li, D Wang Nuclear Fusion 62 (7), 076012, 2022 | 1 | 2022 |
| Modelling of nanometer scale dust grains in tokamak Z Liu, X Xiao, X Xu, N Li, T Tang, D Wang Contributions to Plasma Physics 60 (5-6), e201900136, 2020 | 1 | 2020 |
