Modeling the effect of divertor closure on plasma detachment for new divertor design of EAST by SOLPS
Modeling the effect of divertor closure on plasma detachment for new divertor design of EAST by SOLPS
复制标题
通过 SOLPS 对 EAST 新型偏滤器设计中偏滤器关闭对等离子体脱离的影响进行建模
DOI：
10.1088/1361-6587/ab348f
复制
发表时间：
2019
影响因子：
2.2
通讯作者：
Mao S F
中科院分区：
文献类型：
--
作者：
Si H;Guo H Y;Xu G S;Yao D M;Wang L;Ding R;Luo Z P;Xu J C;Mao S F
One of the major challenges for the design and operation of next-step high-power steady-state fusion devices is to develop and validate advanced divertor solutions for handling power exhaust, while maintaining acceptable divertor target plate erosion. This requires to access divertor detachment at relatively low main plasma densities compatible with current drive and high plasma confinement. Recently a new initiative has been launched on the EAST superconducting tokamak to develop a new divertor for evaluating boundary plasma solutions applicable to the next step fusion experiments beyond ITER. In the present work, four different divertor configurations with different degrees of closure are evaluated through detailed modeling with the SOLPS plasma boundary code. The modeling results show that increasing divertor closure can significantly trap more neutrals from 0.04 × 10 19 to 0.75 × 10 19 m − 3 with the same upstream separatrix density n e , sep OMP = 1.9 × 10 19 m − 3 and hence facilitate the onset of detachment decreasing from 3.20 × 10 19 to 2.14 × 10 19 m − 3 . Moreover, with increasing divertor closure the divertor radiated power is also increased from 200 to 450 kW and the peak heat flux density at the divertor target is reduced from 9.3 to 3.8 MW m−2. Therefore, increasing divertor closure can benefit divertor operation for EAST and may be used as one of the scientific metrics for the divertor design of future fusion devices.
