[1] Prater R. Heating and current drive by electron cyclotron waves[J]. Physics of Plasmas, 11, 2349-2376(2004).

[2] Huang Y H, Xiang N, Chen J L et al. Modeling very high electron heating by radio frequency waves on EAST[J]. Nuclear Fusion, 61, 096026(2021).

[3] Petty C C, Haye R J L, Luce T C et al. Complete suppression of them=2/n=1 neoclassical tearing mode using electron cyclotron current drive in DIII-D[J]. Nuclear Fusion, 44, 243-251(2004).

[4] Sertoli M, Angioni C, Dux R et al. Local effects of ECRH on argon transport in L-mode discharges at ASDEX upgrade[J]. Plasma Physics and Controlled Fusion, 53, 035024(2011).

[5] Beurskens M N A, Dunne M G, Frassinetti L et al. The role of carbon and nitrogen on the H-mode confinement in ASDEX Upgrade with a metal wall[J]. Nuclear Fusion, 56, 056014(2016).

[6] Petrie T W, Osborne T, Fenstermacher M E et al. Improved confinement in highly powered high performance scenarios on DIII-D[J]. Nuclear Fusion, 57, 086004(2017).

[7] Urano H, Nakata M, Aiba N et al. Roles of argon seeding in energy confinement and pedestal structure in JT-60U[J]. Nuclear Fusion, 55, 033010(2015).

[8] Dux R, Neu R, Peeters A G et al. Influence of the heating profile on impurity transport in ASDEX Upgrade[J]. Plasma Physics and Controlled Fusion, 45, 1815-1825(2003).

[9] Fisch N J, Boozer A H. Creating an asymmetric plasma resistivity with waves[J]. Physical Review Letters, 45, 720-722(1980).

[10] Zheng P W, Gong X Y, Lu X Q et al. On current drive by Ohkawa mechanism of electron cyclotron wave in large inverse aspect ratio tokamaks[J]. Nuclear Fusion, 58, 036010(2018).

[11] Meneghini O, Snyder P B, Smith S P et al. Integrated fusion simulation with self-consistent core-pedestal coupling[J]. Physics of Plasmas, 23, 042507(2016).

[12] Chen J L, Chan V S, Jian X et al. Integrated modeling of CFETR hybrid scenario plasmas[J]. Nuclear Fusion, 61, 046002(2021).

[13] Meneghini O, Smith S P, Lao L L et al. Integrated modeling applications for tokamak experiments with OMFIT[J]. Nuclear Fusion, 55, 083008(2015).

[14] Lin Y R, Chan V S, Prater R. Electron cyclotron current drive efficiency in general tokamak geometry[J]. Physics of Plasmas, 10, 4064-4071(2003).

[15] Snyder P B, Groebner R J, Hughes J W et al. A first-principles predictive model of the pedestal height and width: development, testing and ITER optimization with the EPED model[J]. Nuclear Fusion, 51, 103016(2011).

[16] Taylor T S, St John H, Turnbull A D et al. Optimized profiles for improved confinement and stability in the DIII-D tokamak[J]. Plasma Physics and Controlled Fusion, 36, B229-B239(1994).

[17] Lao L L, St John H, Stambaugh R D et al. Reconstruction of current profile parameters and plasma shapes in tokamaks[J]. Nuclear Fusion, 25, 1611-1622(1985).

[18] Pan C, Staebler G M, Lao L L et al. Investigation of energy transport in DIII-D High-βP EAST-demonstration discharges with the TGLF turbulent and NEO neoclassical transport models[J]. Nuclear Fusion, 57, 036018(2017).