EAST steady-state long pulse H-mode with core-edge integration for CFETR

Gong, Xianzu; Garofalo, Andrea M.; Huang, Juan; Qian, Jinping; Ekedahl, Annika; Maingi, Rajesh; Holcomb, Chris T.; Liu, Fukun; Zhao, Yanping; Xiao, Bingjia; Hu, Jiansheng; Hu, Chundong; Hu, Liqun; Wang, Mao; Xu, Handong; Li, Erzhong; Zeng, Long; Zang, Qing; Liu, Haiqing; Lyu, Bo; Yuan, Q. P.; Li, Kedong; Zhang, Bin; Zhang, Jiayuan; Jia, Tianqi; Wu, Muquan; Chen, Jiale; Zhu, Xiang; Li, Miaohui; Zhang, Xinjun; Zhang, Ling; Duan, Yanmin; Wang, Liang; Ding, Rui; Sun, Youwen; Xu, Guo Sheng; Liang, Yunfeng; Xiang, Nong; Wan, Baonian; Li, Jiangang

doi:10.1088/1741-4326/ac49ad

Title: EAST steady-state long pulse H-mode with core-edge integration for CFETR

Abstract

Recent EAST experiment has successfully demonstrated long pulse steady-state high plasma performance scenario and core-edge integration since the last IAEA in 2018. A discharge with a duration over 60s with β_P ~2.0, β_N ~1.6, H_98y2~1.3 and internal transport barrier on electron temperature channel is obtained with multi-RF power heating and current drive. A higher β_N (β_N~1.8, β_p~2.0, H_98y2~1.3, n_e/n_GW~0.75) with a duration of 20s is achieved by using the modulated neutral beam and multi-RF power, where several normalized parameters are close or even higher than the phase III 1GW scenario of CFETR steady-state. High-Z impurity accumulation in the plasma core is well controlled in a low level by using the on-axis ECH. Modelling shows that the strong diffusion of TEM turbulence in the central region prevents tungsten impurity to accumulate. More recently, EAST has demonstrated compatible core-edge integration discharges in the high βp scenario: high confinement H_98y2>1.2 with high β_P~2.5/β_N~2.0 and f_bs~50% is sustained with reduced divertor heat flux at high density n_e/n_GW~0.7 and moderate q₉₅~6.7. By combining active impurity seeding through radiative divertor feedback control and strike point splitting induced by resonant perturbation coil, the peak heat flux is reduced by 20-30% on the ITER-like tungsten divertor, here amore »« less

Authors:

Gong, Xianzu ^[1];

^[2]; Huang, Juan ^[1]; Qian, Jinping ^[1]; Ekedahl, Annika ^[3];

^[4]; Holcomb, Chris T. ^[5]; Liu, Fukun ^[1]; Zhao, Yanping ^[1]; Xiao, Bingjia ^[1]; Hu, Jiansheng ^[1]; Hu, Chundong ^[1]; Hu, Liqun ^[1]; Wang, Mao ^[1]; Xu, Handong ^[1];

^[1];

^[1]; Zang, Qing ^[1];

^[1];

^[1] more »

Chinese Academy of Sciences (CAS), Beijing (China)
General Atomics, San Diego, CA (United States)
Alternative Energies and Atomic Energy Commission (CEA), Saint Paul-lez-Durance (France)
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

Publication Date:: Tue Apr 26 00:00:00 EDT 2022

Research Org.:: General Atomics, San Diego, CA (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); National MCF Energy R&D Program; National Natural Science Foundation of China (NSFC); Anhui Provincial Natural Science Foundation; Chinese Academy of Sciences

OSTI Identifier:: 1855250

Grant/Contract Number:: SC0010685; 2019YFE03040000; 2019YFE03020004; 11975274; 12005262; 11975276; 2021HSC-UE018; 2020HSC-UE011; 116134KYSB20180035; 2108085J06; 2008085J04; DSJJ-2021-04

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Fusion

Additional Journal Information:: Journal Volume: 62; Journal Issue: 7; Journal ID: ISSN 0029-5515

Publisher:: IOP Science

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats


                    Gong, Xianzu, Garofalo, Andrea M., Huang, Juan, Qian, Jinping, Ekedahl, Annika, Maingi, Rajesh, Holcomb, Chris T., Liu, Fukun, Zhao, Yanping, Xiao, Bingjia, Hu, Jiansheng, Hu, Chundong, Hu, Liqun, Wang, Mao, Xu, Handong, Li, Erzhong, Zeng, Long, Zang, Qing, Liu, Haiqing, Lyu, Bo, Yuan, Q. P., Li, Kedong, Zhang, Bin, Zhang, Jiayuan, Jia, Tianqi, Wu, Muquan, Chen, Jiale, Zhu, Xiang, Li, Miaohui, Zhang, Xinjun, Zhang, Ling, Duan, Yanmin, Wang, Liang, Ding, Rui, Sun, Youwen, Xu, Guo Sheng, Liang, Yunfeng, Xiang, Nong, Wan, Baonian, and Li, Jiangang. EAST steady-state long pulse H-mode with core-edge integration for CFETR.  United States: N. p., 2022. 
Web.  doi:10.1088/1741-4326/ac49ad.

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                    Gong, Xianzu, Garofalo, Andrea M., Huang, Juan, Qian, Jinping, Ekedahl, Annika, Maingi, Rajesh, Holcomb, Chris T., Liu, Fukun, Zhao, Yanping, Xiao, Bingjia, Hu, Jiansheng, Hu, Chundong, Hu, Liqun, Wang, Mao, Xu, Handong, Li, Erzhong, Zeng, Long, Zang, Qing, Liu, Haiqing, Lyu, Bo, Yuan, Q. P., Li, Kedong, Zhang, Bin, Zhang, Jiayuan, Jia, Tianqi, Wu, Muquan, Chen, Jiale, Zhu, Xiang, Li, Miaohui, Zhang, Xinjun, Zhang, Ling, Duan, Yanmin, Wang, Liang, Ding, Rui, Sun, Youwen, Xu, Guo Sheng, Liang, Yunfeng, Xiang, Nong, Wan, Baonian, & Li, Jiangang. EAST steady-state long pulse H-mode with core-edge integration for CFETR.  United States.  https://doi.org/10.1088/1741-4326/ac49ad

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                    Gong, Xianzu, Garofalo, Andrea M., Huang, Juan, Qian, Jinping, Ekedahl, Annika, Maingi, Rajesh, Holcomb, Chris T., Liu, Fukun, Zhao, Yanping, Xiao, Bingjia, Hu, Jiansheng, Hu, Chundong, Hu, Liqun, Wang, Mao, Xu, Handong, Li, Erzhong, Zeng, Long, Zang, Qing, Liu, Haiqing, Lyu, Bo, Yuan, Q. P., Li, Kedong, Zhang, Bin, Zhang, Jiayuan, Jia, Tianqi, Wu, Muquan, Chen, Jiale, Zhu, Xiang, Li, Miaohui, Zhang, Xinjun, Zhang, Ling, Duan, Yanmin, Wang, Liang, Ding, Rui, Sun, Youwen, Xu, Guo Sheng, Liang, Yunfeng, Xiang, Nong, Wan, Baonian, and Li, Jiangang. Tue .  
"EAST steady-state long pulse H-mode with core-edge integration for CFETR".  United States.  https://doi.org/10.1088/1741-4326/ac49ad.  https://www.osti.gov/servlets/purl/1855250.

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@article{osti_1855250,

  title        = {EAST steady-state long pulse H-mode with core-edge integration for CFETR},

  author       = {Gong, Xianzu and Garofalo, Andrea M. and Huang, Juan and Qian, Jinping and Ekedahl, Annika and Maingi, Rajesh and Holcomb, Chris T. and Liu, Fukun and Zhao, Yanping and Xiao, Bingjia and Hu, Jiansheng and Hu, Chundong and Hu, Liqun and Wang, Mao and Xu, Handong and Li, Erzhong and Zeng, Long and Zang, Qing and Liu, Haiqing and Lyu, Bo and Yuan, Q. P. and Li, Kedong and Zhang, Bin and Zhang, Jiayuan and Jia, Tianqi and Wu, Muquan and Chen, Jiale and Zhu, Xiang and Li, Miaohui and Zhang, Xinjun and Zhang, Ling and Duan, Yanmin and Wang, Liang and Ding, Rui and Sun, Youwen and Xu, Guo Sheng and Liang, Yunfeng and Xiang, Nong and Wan, Baonian and Li, Jiangang},

  abstractNote = {Recent EAST experiment has successfully demonstrated long pulse steady-state high plasma performance scenario and core-edge integration since the last IAEA in 2018. A discharge with a duration over 60s with βP ~2.0, βN ~1.6, H98y2~1.3 and internal transport barrier on electron temperature channel is obtained with multi-RF power heating and current drive. A higher βN (βN~1.8, βp~2.0, H98y2~1.3, ne/nGW~0.75) with a duration of 20s is achieved by using the modulated neutral beam and multi-RF power, where several normalized parameters are close or even higher than the phase III 1GW scenario of CFETR steady-state. High-Z impurity accumulation in the plasma core is well controlled in a low level by using the on-axis ECH. Modelling shows that the strong diffusion of TEM turbulence in the central region prevents tungsten impurity to accumulate. More recently, EAST has demonstrated compatible core-edge integration discharges in the high βp scenario: high confinement H98y2>1.2 with high βP~2.5/βN~2.0 and fbs~50% is sustained with reduced divertor heat flux at high density ne/nGW~0.7 and moderate q95~6.7. By combining active impurity seeding through radiative divertor feedback control and strike point splitting induced by resonant perturbation coil, the peak heat flux is reduced by 20-30% on the ITER-like tungsten divertor, here a mixture of 50% neon and 50% D2 is applied.},

  doi          = {10.1088/1741-4326/ac49ad},

  journal      = {Nuclear Fusion},

  number       = 7,

  volume       = 62,

  place        = {United States},

  year         = {Tue Apr 26 00:00:00 EDT 2022},

  month        = {Tue Apr 26 00:00:00 EDT 2022}

}

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Works referenced in this record:

Modeling and advances in the high bootstrap fraction regime on EAST towards the steady-state operation
journal, August 2019

Wu, M. Q.; Li, G. Q.; Qian, J. P.
Nuclear Fusion, Vol. 59, Issue 10
DOI: 10.1088/1741-4326/ab2d60

Interplay between central ECRH and saturated ( m , n ) = (1, 1) MHD activity in mitigating tungsten accumulation at ASDEX Upgrade
journal, September 2015

Sertoli, M.; Odstrcil, T.; Angioni, C.
Nuclear Fusion, Vol. 55, Issue 11
DOI: 10.1088/0029-5515/55/11/113029

Detachment plasma achieved based on active temperature feedback system in EAST
journal, June 2020

Chen, M. W.; Gong, X. Z.; Gan, K. F.
Nuclear Fusion, Vol. 60, Issue 7
DOI: 10.1088/1741-4326/ab8c65

A comparison of the impact of central ECRH and central ICRH on the tungsten behaviour in ASDEX Upgrade H-mode plasmas
journal, March 2017

Angioni, C.; Sertoli, M.; Bilato, R.
Nuclear Fusion, Vol. 57, Issue 5
DOI: 10.1088/1741-4326/aa6453

Overview of EAST experiments on the development of high-performance steady-state scenario
journal, July 2017

Wan, B. N.; Liang, Y. F.; Gong, X. Z.
Nuclear Fusion, Vol. 57, Issue 10
DOI: 10.1088/1741-4326/aa7861

Nonlinear gyrokinetic simulation of ion temperature gradient turbulence based on a numerical Lie-transform perturbation method
journal, August 2017

Xu, Yingfeng; Ye, Lei; Dai, Zongliang
Physics of Plasmas, Vol. 24, Issue 8
DOI: 10.1063/1.4986395

Advances in the high bootstrap fraction regime on DIII-D towards the Q = 5 mission of ITER steady state
journal, March 2017

Qian, J. P.; Garofalo, A. M.; Gong, X. Z.
Nuclear Fusion, Vol. 57, Issue 5
DOI: 10.1088/1741-4326/aa626a

Scenario development for high β _p low torque plasma with q _min above 2 and large-radius internal transport barrier in DIII-D
journal, September 2016

Ding, S.; Xu, G. S.; Wang, Q.
Nuclear Fusion, Vol. 57, Issue 2
DOI: 10.1088/0029-5515/57/2/022016

Progress of the CFETR design
journal, June 2019

Zhuang, G.; Li, G. Q.; Li, J.
Nuclear Fusion, Vol. 59, Issue 11
DOI: 10.1088/1741-4326/ab0e27

Time diffusion method for gyrokinetic simulation of electrostatic turbulence with kinetic electrons
journal, December 2021

Zhao, PengFei; Ye, Lei; Xiang, Nong
Computer Physics Communications, Vol. 269
DOI: 10.1016/j.cpc.2021.108114

Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST
journal, June 2017

Garofalo, A. M.; Gong, X. Z.; Qian, J.
Nuclear Fusion, Vol. 57, Issue 7
DOI: 10.1088/1741-4326/aa7186

Progress toward steady-state tokamak operation exploiting the high bootstrap current fraction regime
journal, June 2016

Ren, Q. L.; Garofalo, A. M.; Gong, X. Z.
Physics of Plasmas, Vol. 23, Issue 6
DOI: 10.1063/1.4948724

EAST equilibrium current profile reconstruction using polarimeter-interferometer internal measurement constraints
journal, December 2016

Qian, J. P.; Lao, L. L.; Liu, H. Q.
Nuclear Fusion, Vol. 57, Issue 3
DOI: 10.1088/1741-4326/aa4e58

Experimental and theoretical study of nickel transport dependence on gradients in Tore Supra
journal, April 2014

Villegas, D.; Guirlet, R.; Bourdelle, C.
Nuclear Fusion, Vol. 54, Issue 7
DOI: 10.1088/0029-5515/54/7/073011

Modification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas
journal, February 2017

Hong, Joohwan; Henderson, S. S.; Kim, Kimin
Nuclear Fusion, Vol. 57, Issue 3
DOI: 10.1088/1741-4326/aa5333

Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR
journal, December 2019

Huang, J.; Gong, X.; Garofalo, A. M.
Plasma Physics and Controlled Fusion, Vol. 62, Issue 1
DOI: 10.1088/1361-6587/ab56a5

A gyrokinetic continuum code based on the numerical Lie transform (NLT) method
journal, July 2016

Ye, Lei; Xu, Yingfeng; Xiao, Xiaotao
Journal of Computational Physics, Vol. 316
DOI: 10.1016/j.jcp.2016.03.068

Improved high-performance fully non-inductive discharge by optimizing the fast-ion confinement on EAST
journal, October 2019

Huang, J.; Qian, J. P.; Garofalo, A. M.
Nuclear Fusion, Vol. 60, Issue 1
DOI: 10.1088/1741-4326/ab443a

Achievement of radiative feedback control for long-pulse operation on EAST
journal, March 2018

Wu, K.; Yuan, Q. P.; Xiao, B. J.
Nuclear Fusion, Vol. 58, Issue 5
DOI: 10.1088/1741-4326/aab506

Advances in physics understanding of high poloidal beta regime toward steady-state operation of CFETR
journal, April 2021

Qian, J. P.; Garofalo, A. M.; Gong, X. Z.
Physics of Plasmas, Vol. 28, Issue 4
DOI: 10.1063/5.0032490

Kinetic calculation of neoclassical transport including self-consistent electron and impurity dynamics
journal, July 2008

Belli, E. A.; Candy, J.
Plasma Physics and Controlled Fusion, Vol. 50, Issue 9
DOI: 10.1088/0741-3335/50/9/095010

Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST
journal, May 2017

Ding, S.; Garofalo, A. M.; Qian, J.
Physics of Plasmas, Vol. 24, Issue 5
DOI: 10.1063/1.4982058

Core tungsten transport in WEST long pulse L-mode plasmas
journal, July 2020

Yang, X.; Manas, P.; Bourdelle, C.
Nuclear Fusion, Vol. 60, Issue 8
DOI: 10.1088/1741-4326/ab9669

Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak
journal, July 2019

Gong, X.; Garofalo, A. M.; Huang, J.
Nuclear Fusion, Vol. 59, Issue 8
DOI: 10.1088/1741-4326/ab1c7b

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR
journal, November 2017

Garofalo, A. M.; Gong, X. Z.; Ding, S. Y.
Plasma Physics and Controlled Fusion, Vol. 60, Issue 1
DOI: 10.1088/1361-6587/aa8c9d

Compatibility of internal transport barrier with steady-state operation in the high bootstrap fraction regime on DIII-D
journal, November 2015

Garofalo, A. M.; Gong, X.; Grierson, B. A.
Nuclear Fusion, Vol. 55, Issue 12
DOI: 10.1088/0029-5515/55/12/123025

Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier
journal, October 2003

Takenaga, H.; Higashijima, S.; Oyama, N.
Nuclear Fusion, Vol. 43, Issue 10
DOI: 10.1088/0029-5515/43/10/026

Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST
journal, July 2019

Wang, L.; Guo, H. Y.; Ding, F.
Nuclear Fusion, Vol. 59, Issue 8
DOI: 10.1088/1741-4326/ab1ed4

Core turbulent transport in tokamak plasmas: bridging theory and experiment with QuaLiKiz
journal, December 2015

Bourdelle, C.; Citrin, J.; Baiocchi, B.
Plasma Physics and Controlled Fusion, Vol. 58, Issue 1
DOI: 10.1088/0741-3335/58/1/014036

Dependence of the impurity transport on the dominant turbulent regime in ELM-y H-mode discharges on the DIII-D tokamak
journal, August 2020

Odstrčil, T.; Howard, N. T.; Sciortino, F.
Physics of Plasmas, Vol. 27, Issue 8
DOI: 10.1063/5.0010725

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Title: EAST steady-state long pulse H-mode with core-edge integration for CFETR

Abstract

Citation Formats

Modeling and advances in the high bootstrap fraction regime on EAST towards the steady-state operation journal, August 2019

Interplay between central ECRH and saturated ( m , n ) = (1, 1) MHD activity in mitigating tungsten accumulation at ASDEX Upgrade journal, September 2015

Detachment plasma achieved based on active temperature feedback system in EAST journal, June 2020

A comparison of the impact of central ECRH and central ICRH on the tungsten behaviour in ASDEX Upgrade H-mode plasmas journal, March 2017

Overview of EAST experiments on the development of high-performance steady-state scenario journal, July 2017

Nonlinear gyrokinetic simulation of ion temperature gradient turbulence based on a numerical Lie-transform perturbation method journal, August 2017

Advances in the high bootstrap fraction regime on DIII-D towards the Q = 5 mission of ITER steady state journal, March 2017

Scenario development for high β p low torque plasma with q min above 2 and large-radius internal transport barrier in DIII-D journal, September 2016

Progress of the CFETR design journal, June 2019

Time diffusion method for gyrokinetic simulation of electrostatic turbulence with kinetic electrons journal, December 2021

Development of high poloidal beta, steady-state scenario with ITER-like tungsten divertor on EAST journal, June 2017

Progress toward steady-state tokamak operation exploiting the high bootstrap current fraction regime journal, June 2016

EAST equilibrium current profile reconstruction using polarimeter-interferometer internal measurement constraints journal, December 2016

Experimental and theoretical study of nickel transport dependence on gradients in Tore Supra journal, April 2014

Modification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas journal, February 2017

Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR journal, December 2019

A gyrokinetic continuum code based on the numerical Lie transform (NLT) method journal, July 2016

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Achievement of radiative feedback control for long-pulse operation on EAST journal, March 2018

Advances in physics understanding of high poloidal beta regime toward steady-state operation of CFETR journal, April 2021

Kinetic calculation of neoclassical transport including self-consistent electron and impurity dynamics journal, July 2008

Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST journal, May 2017

Core tungsten transport in WEST long pulse L-mode plasmas journal, July 2020

Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak journal, July 2019

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR journal, November 2017

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Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST journal, July 2019

Core turbulent transport in tokamak plasmas: bridging theory and experiment with QuaLiKiz journal, December 2015

Dependence of the impurity transport on the dominant turbulent regime in ELM-y H-mode discharges on the DIII-D tokamak journal, August 2020

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journal, August 2019

Interplay between central ECRH and saturated ( m , n ) = (1, 1) MHD activity in mitigating tungsten accumulation at ASDEX Upgrade
journal, September 2015

Detachment plasma achieved based on active temperature feedback system in EAST
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A comparison of the impact of central ECRH and central ICRH on the tungsten behaviour in ASDEX Upgrade H-mode plasmas
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Overview of EAST experiments on the development of high-performance steady-state scenario
journal, July 2017

Nonlinear gyrokinetic simulation of ion temperature gradient turbulence based on a numerical Lie-transform perturbation method
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journal, March 2017

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journal, December 2021

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journal, June 2017

Progress toward steady-state tokamak operation exploiting the high bootstrap current fraction regime
journal, June 2016

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journal, April 2014

Modification of argon impurity transport by electron cyclotron heating in KSTAR H-mode plasmas
journal, February 2017

Progress of physics understanding for long pulse high-performance plasmas on EAST towards the steady-state operation of ITER and CFETR
journal, December 2019

A gyrokinetic continuum code based on the numerical Lie transform (NLT) method
journal, July 2016

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journal, October 2019

Achievement of radiative feedback control for long-pulse operation on EAST
journal, March 2018

Advances in physics understanding of high poloidal beta regime toward steady-state operation of CFETR
journal, April 2021

Kinetic calculation of neoclassical transport including self-consistent electron and impurity dynamics
journal, July 2008

Confinement improvement in the high poloidal beta regime on DIII-D and application to steady-state H-mode on EAST
journal, May 2017

Core tungsten transport in WEST long pulse L-mode plasmas
journal, July 2020

Integrated operation of steady-state long-pulse H-mode in Experimental Advanced Superconducting Tokamak
journal, July 2019

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR
journal, November 2017

Compatibility of internal transport barrier with steady-state operation in the high bootstrap fraction regime on DIII-D
journal, November 2015

Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier
journal, October 2003

Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST
journal, July 2019

Core turbulent transport in tokamak plasmas: bridging theory and experiment with QuaLiKiz
journal, December 2015

Dependence of the impurity transport on the dominant turbulent regime in ELM-y H-mode discharges on the DIII-D tokamak
journal, August 2020