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

EAST steady-state long pulse H-mode with core-edge integration for CFETR
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DOI:
10.1088/1741-4326/ac49ad
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发表时间:
2022-01
期刊:
影响因子:
3.3
通讯作者:
X. Gong;A. Garofalo;J. Huang;J. Qian;A. Ekedah;R. Maingi;C. Holcomb;F. Liu;Y.P. Zhao;B. Xiao;J.S. Hu;C.D. Hu;L. Hu;M. Wang;H.D. Xu;E. Li;L. Zeng;Q. Zang;H.Q. Liu;B. Lyu;Q. Yuan;K.D. Li;B. Zhang;J.Y. Zhang;T. Jia;M.Q. Wu;J.L. Chen;X. Zhu;M.H. Li;X.J. Zhang;L. Zhang;Y. Duan;Liang Wang;R. Ding;Y.W. Sun;G.S. Xu;Y.F. Liang;N. Xiang;B. Wan;J.G. Li
X. Gong;A. Garofalo;J. Huang;J. Qian;A. Ekedah;R. Maingi;C. Holcomb;F. Liu;Y.P. Zhao;B. Xiao;J.S. Hu;C.D. Hu;L. Hu;M. Wang;H.D. Xu;E. Li;L. Zeng;Q. Zang;H.Q. Liu;B. Lyu;Q. Yuan;K.D. Li;B. Zhang;J.Y. Zhang;T. Jia;M.Q. Wu;J.L. Chen;X. Zhu;M.H. Li;X.J. Zhang;L. Zhang;Y. Duan;Liang Wang;R. Ding;Y.W. Sun;G.S. Xu;Y.F. Liang;N. Xiang;B. Wan;J.G. Li
中科院分区:
物理与天体物理1区
文献类型:
--
作者:
X. Gong;A. Garofalo;J. Huang;J. Qian;A. Ekedah;R. Maingi;C. Holcomb;F. Liu;Y.P. Zhao;B. Xiao;J.S. Hu;C.D. Hu;L. Hu;M. Wang;H.D. Xu;E. Li;L. Zeng;Q. Zang;H.Q. Liu;B. Lyu;Q. Yuan;K.D. Li;B. Zhang;J.Y. Zhang;T. Jia;M.Q. Wu;J.L. Chen;X. Zhu;M.H. Li;X.J. Zhang;L. Zhang;Y. Duan;Liang Wang;R. Ding;Y.W. Sun;G.S. Xu;Y.F. Liang;N. Xiang;B. Wan;J.G. Li

文献摘要

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自2018年上一次IAEA以来,最近的EAST实验成功地证明了长脉冲稳态高等离子体性能场景和核心边缘集成。在多射频功率加热和电流驱动下,获得了持续时间超过60 s的放电,放电参数为β P ≤ 2.0,β N ≤ 1.6,H_(98)y_2 ≤ 1.3,电子温度通道上存在内输运势垒。采用调制中性束和多射频功率实现了持续时间为20 s的较高β N(β N <$1.8,β p <$2.0,H98 y2 <$1.3,ne/n GW <$0.75),其中几个归一化参数接近甚至高于CFETR稳态III期1 GW场景。利用轴上ECH,等离子体芯中的高Z杂质积累被很好地控制在低水平。模拟表明,TEM湍流在中心区域的强扩散阻止了钨杂质的积累。最近,EAST已经证明了在高β p情况下相容的堆芯-边缘一体化放电:高约束H98 y2> 1.2,高β P ≥ 2.5/β N ≥ 2.0,fbs ≥ 50%,在高密度n e/n GW ≥ 0.7和中等q 95 ≤ 6.7时,偏滤器热通量降低。在类ITER钨偏滤器上,通过辐射偏滤器反馈控制注入活性杂质和共振微扰线圈诱导撞击点分裂相结合,峰值热流降低了20-30%,这里采用的是氖和50%D2的混合物。
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, H98y2 ∼ 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, H98y2 ∼ 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 H98y2 > 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% D2 is applied.