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电流压缩实验

HT-7. 电流压缩实验. Presented by Yuejiang Shi. 实验目的. 研究电流压缩实验过程中的锯齿稳定化现象，探索利用电流压缩的手段实现具有  N 或者 H-mode 或者 ITB 性质的高约束状态的等离子体。. 国外装置的 CRD 实验. JIPP T-IIU,COMPASS-D 和 TUMAN-3M 通过电流压缩实现了 H 模。 COMPASS-D 和 FTU 在电流压缩实验中观察到了芯部约束改善和边界输运垒.

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电流压缩实验

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  1. HT-7 电流压缩实验 Presented by Yuejiang Shi

  2. 实验目的 • 研究电流压缩实验过程中的锯齿稳定化现象，探索利用电流压缩的手段实现具有N或者H-mode或者ITB性质的高约束状态的等离子体。

  3. 国外装置的CRD实验 • JIPP T-IIU,COMPASS-D和TUMAN-3M通过电流压缩实现了H模。 • COMPASS-D和FTU在电流压缩实验中观察到了芯部约束改善和边界输运垒

  4. COMPASS-D:Ohmic discharge with CRD results in production of ELM-free H-mode. JIPP TII-U: Ely H-mode was triggered by CRD in the RF heating discharge

  5. HT-7的实验结果 Stabilization of Sawtooth is achieved during current ramp-dwon phase and sustained after current ramp-down. The electron temperature of core plasma is greatly increased

  6. 放电要求 • 等离子体参数： • 中心弦平均密度1.5 • 等离子体希望维持1.6秒的平台，压缩前的等离子体电流160kA,压缩后100kA, • 低杂波从300ms投入，等离子电流从700ms开始压缩，低杂波功率在电流压缩前后维持不变,低杂波做200kW，250kW，300kW，350kW和400kW的功率扫描。 • 同样条件下的160kA和100kA的非电流压缩的300kW和400kW的LHCD对比实验各做一组 • 不加LHW的OH电流压缩实验做一组

  7. HT-7 Proposal of Magnetic Shear Reversal Experiments in HT-7 Presented by Yuejiang Shi

  8. Steady-state advanced tokamak scenarios will necessarily have a high bootstrap fraction. Since the ‘natural’ profile of the bootstrap current is a hollow current profile, it becomes natural to ask what is the performance potential for such profiles. The RS/NCS regime combines high confinement, potentially high beta limits with wall stabilization, high bootstrap fraction with well-aligned bootstrap current. .

  9. ITB is closely related with RS ITBs are affected by the extent of shear reversal (JT-60U). (a) strongly reversed (b) weakly reversed (c) monotonic

  10. ITBs in all three profiles (Ne,Te, Ti) can be obtained in RS plasma (JT-60U). ITB in Te can be observed only with strong RS in JT-60U and JET.

  11. Confinement is significantly improved in enhanced reversed shear (TFTR).

  12. The stabilization of microturbulence by sheared EB flow is the leading explanation for the reduction in transport RS discharge. But EB is not the one and only mechanism. TFTR: (a) ERS transition (b) no transition

  13. The central plasma rotation in LHEP discharges in Tore Supra is not sufficient for EB stabilization, and the ion pressure is also expected not to contribute significantly to E  B shear. Like Tore Supra, significantly e reduction only can be observed with strong negative magnetic shear mode in DIII-D and JT-60U. Shear EB flow is not sufficient to explain the improvement of electron confinement. Electron transport is observed to decrease with increasingly more negative magnetic shear in Tore Supra LHCD discharges

  14. The often used technique to achieve RS: auxiliary preheating during current ramp-up phase DIII-D:NBI preheating is applied during current ramp-up phase. RS is sustained by NBI.

  15. JT-60U:NBI preheating is applied during current ramp-up phase. RS is sustained by off-axis LHCD.

  16. Different preheating methods (LHCD, ICRH and ohmic) have been verified in JET. LHCD preheating is the most effective to achieve RS.

  17. Tore Supra: Both formation and sustainment of RS can be achieved by off-axis LHCD.

  18. TCV: RS is obtained by co-off-axis and cnt-on-axis ECCD.

  19. Proposal of magnetic shear reversal experiments in HT-7 • 等离子体参数：中心弦平均密度1.5

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