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10–15 May 2021
Virtual Event
Europe/Vienna timezone
The Conference will be held virtually from 10-15 May 2021

Development of Quiescent H-mode Scenario with ITER-like Tungsten Divertor in EAST

11 May 2021, 14:00
4h 45m
Virtual Event

Virtual Event

Regular Poster Magnetic Fusion Experiments P2 Posters 2

Speaker

Jinping Qian (Institute of plasma physics, Chinese academy of sciences)

Description

Experiments have been carried out to explore quiescent H-mode (QH-mode) $[1]$ scenario under the condition of low torque and pure RF injection (true zero torque) with ITER like tungsten divertor on EAST, which will facilitate the eventual use of this scenario on ITER and other reactors. EAST achieved the stationary QH-mode over 50-80 energy confinement time or 3-6 current relaxation time with the energy confinement close or slightly below $H_{98,y2}$ scaling ($H_{98,y2}$ ≤ 1.0) by using counter and co-Ip neutral beams (-0.5 Nm ≤ $T_{inj}$ ≤ -1.0 Nm) or pure RF power with non-resonant magnetic fields (NRMF) in separated experiments. Characteristics of coherent modes or broadband MHD fluctuations with enhancing the edge turbulence transport and replacing ELMs during QH-mode phase are observed from the spectrum analysis of Mirnov probes, microwave reflectometer and other diagnostics.

EAST first QH-mode was accessed by using the counter NB to produce plasma rotation in the counter direction. Results show that stationary ELM-free regime obtained more easily with lower recycling and stronger counter NBI torque. Figure 1 shows an example of QH-mode discharge ($I_p$~0.5MA, $B_T$=2.5T, $q_95$~5.0) with ELM free from 3.5s to 7.0s. The plasma configuration is an upper single null (USN) with the strike points on the tungsten divertor. The two counter NBs were used to access QH-mode and then one counter NB was schemed to maintain this regime, where the beam energy was optimized to mitigate the prompt fast ion losses for reduced impurity influx, together with zero gas feed-forward after 2.2s. The spectrum analysis shows that coherent multi-harmonic modes ($f$ ~60/120kHz $n$=-1/-2) appear to replace ELMs. Here n is the toroidal mode number.
Time histories of several parameters of QH mode discharge by using counter neutral beam in EAST. From top to bottom, plasma current (Ip) and Da; the injected power of NB, LHW and EC; magnetic fluctuation spectra by Mirnov probe; the feed forward gas and line averaged density.

Experiments on the exploration of lower torque have shown that QH-mode can be achieved by using near balanced NBI at low recycling high density regime. The coherent modes become weak and change to broadband fluctuations with more balanced NBI, similar to the previous DIII-D experiments $[2]$. The relative high density (<$n_e$>/$n_{GW}$~0.6) operation might be a knob in this experiment which can reduce the shine-through and fast ion loss because EAST NB has the small tangential tilt angle.$[2]$

Using the 3D fields, EAST recently achieved the QH-mode with the RF only heating, suggesting that QH-mode can be obtained from a start with zero injected torque rather than ramping the torque down from a high value $[3]$. Figure 2 presents a typical discharge of QH-mode ($I_p$~0.5MA, $B_T$=2.5T, $P_{LHW}$=3.5MW, $P_{EC}$=0.9MW, $q_{95}$~5.0, USN) with the application of n=2 non-resonant rotating field, where the upper array coils phase rotated 3 periods within 2.5s. ELMs completely disappeared and were replaced by the quasi-coherent/broadband MHD fluctuations from 3.5s to 6.5s. ELMs came back after 6.5s suggesting that the NRMF on the plasma edge is the dominant effect. Note that the RF power coupling was also a challenge with the reduced or zero gas puff.
Time histories of several parameters of QH mode discharge by using pure RF and NRMF. From top to bottom, the injected power of LHW and EC, Da, feed-forward gas puff, n=2 NRMF and magnetic fluctuation spectra by Mirnov probe.

In summary, recent EAST experiments demonstrated QH-mode scenarios with near balanced NBI and with RF-only heating. More analysis of experimental data from core and edge diagnostics is ongoing, to investigate edge stability and particle transport. With the upgrades $[4]$ in 2020, EAST will be capable to further extend QH regime towards more reactor relevant by exploiting two extra ECH gyrotrons and the condition of full metal walls.

This work was supported in part by National Natural Science Foundation of China under Grant No. 11975274, US Department of Energy under DE-SC0010685 and DE-FC02-04ER54698.

$[1]$ Greenfield C.M. et al 2001 Phys. Rev. Lett. 86 4544
$[2]$ Garofalo A. M. et al 2015 Phys. Plasmas 22 056116
$[3]$ Garofalo A.M. et al 2011 Nucl. Fusion 51 083018
$[4]$ Wan B. et al this conference

Affiliation Institute of plasma physics, Chinese academy of sciences
Country or International Organization China

Primary author

Jinping Qian (Institute of plasma physics, Chinese academy of sciences)

Co-authors

A. M. Garofalo (General Atomics) Xianzu Gong (Insititute of Plasma Physics, Chinese Academy Sciences) Dr Bin Zhang (Institute of Plasma Physics, Chinese Academy of Sciences) Dr Tonghui Shi (Institute of plasma physics, Chinese academy of sciences) Dr Long Zeng Mr QUN Ma (Institute of plasma physics, Chinese academy of sciences) Dr Liqing Xu (Institute of plasma physics, Chinese academy of sciences) Juan Huang (CnIPPCAS) Christopher T. Holcomb (Lawrence Livermore National Laboratory) David Weisberg (General Atomics) Mr Muquan Wu (Institute of Plasma Physics, Chinese Academy of Sciences) Jiale Chen Siye Ding (Institute of Plasma Physics, Chinese Academy of Sciences) Dr Qing Zang (institute of plasma physics, Chinese academy of sciences) Bo Lyu (Institute of Plasma Physics, Chinese Academy of Sciences) Dr Haiqing Liu (Institute of plasma physics, Chinese academy of sciences) Youwen Sun (Institute of Plasma Physics, Chinese Academy of Scienses)

Presentation materials