Advances in plasma-wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST
Advances in plasma-wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST
复制标题
EAST 上使用类似 ITER 的钨偏滤器在 H 模式运行 100 秒以上的等离子体壁相互作用控制方面取得进展
DOI：
10.1088/1741-4326/ab1ed4
复制
发表时间：
2019
期刊：
影响因子：
3.3
通讯作者：
Liang
中科院分区：
文献类型：
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作者：
Wang L;Guo H Y;Ding F;Yu Y W;Yuan Q P;Xu G S;Wang H Q;Zhang L;Ding R;Xu J C;Liu J B;Zhang B;Wu K;Li K D;Duan Y M;Luo Z P;Wu J H;Zuo G Z;Sun Z;Eldon D;Leonard A W;Petrie T;Hyatt A;Humphreys D;Thomas D;Yang Z S;Chen X H;Feng W;Chen L;Meng L Y;Qian X Y;Liang
在EAST长脉冲H模式运行101.2 s时，利用ITER式水冷钨（W）单块偏滤器实现了高达0.3 GJ的总功率注入，其稳态功率排放能力为10 MWm− 2。W靶的峰值温度在12 s时饱和到T值~ 500 C，在放电期间保持热通量~ 3.3 MW m− 2。通过边缘磁拓扑结构的改变来调整偏滤器等离子体的三维覆盖区，热负荷被广泛地分散，从而很好地控制了峰值热通量和W溅射。采用D2加料或偏滤器杂质籽晶，成功地实现了H模分离的主动反馈控制，并与堆芯等离子体性能具有良好的兼容性。在H模式运行中，利用氖粒子的辐射功率实现了主动反馈控制，frad = 18%-41%，显示出偏滤器和边缘辐射降低热流密度的潜力。这一点在DIII-D/EAST联合实验中的DIII-D高β P H模方案中得到了进一步证明，该实验使用了偏滤器体积中的杂质播种。稳态粒子控制和杂质排气已经实现了长脉冲H模式操作超过100 s的W偏滤器，通过利用漂移和优化偏滤器配置的效果，加上强泵浦和广泛的壁调节。对偏滤器W源，这是一个金属壁托卡马克至关重要的减少的方法进行了探讨。这些进展为EAST、ITER和CFETR的高功率、长脉冲H模运行提供了重要的实验信息。
A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which has steady-state power exhaust capability of 10 MWm− 2. The peak temperature of W target saturated at 12 s to the value T~ 500 C with a heat flux~ 3.3 MW m− 2 being maintained during the discharge. By tailoring the 3D divertor plasma footprint through edge magnetic topology change, the heat load was broadly dispersed and thus peak heat flux and W sputtering were well controlled. Active feedback control of H-mode detachment with D 2 fuelling or divertor impurity seeding has been achieved successfully, with excellent compatibility with the core plasma performance. Active feedback control of radiative power utilizing neon seeding was achieved with f rad= 18%–41% in H-mode operation, exhibiting potential for heat flux reduction with divertor and edge radiation. This has been further demonstrated in DIII-D high β P H-mode scenario within the joint DIII-D/EAST experiment using impurity seeding from the divertor volume. Steady-state particle control and impurity exhaust has been achieved for long pulse H-mode operation over 100 s with the W divertor by leveraging the effect of drifts and optimized divertor configuration, coupled with strong pumping and extensive wall conditioning. Approaches toward the reduction of divertor W sourcing, which is of crucial importance for a metal-wall tokamak, are also explored. These advances provide important experimental information on favourable core-edge integration for high power, long-pulse H-mode operation in EAST, ITER and CFETR.