EAST steady-state long pulse H-mode with core-edge integration for CFETR
A 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 60 s with β P ∼ 2.0, β N ∼ 1.6, H 98y2 ∼ 1.3 and an internal transport barrier on the electron tempe...
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Veröffentlicht in: | Nuclear fusion 2022-07, Vol.62 (7), p.76009 |
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Format: | Artikel |
Sprache: | eng |
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Zusammenfassung: | A 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 60 s with
β
P
∼ 2.0,
β
N
∼ 1.6, H
98y2
∼ 1.3 and an internal transport barrier on the 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 20 s 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 1 GW 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. Modeling shows that the strong diffusion of TEM turbulence in the central region prevents tungsten impurity from accumulating. More recently, EAST has demonstrated compatible core-edge integration discharges in the high
β
p
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
q
95
∼ 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% D
2
is applied. |
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ISSN: | 0029-5515 1741-4326 |
DOI: | 10.1088/1741-4326/ac49ad |