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Divertor power exhaust with Ar impurity seeding for CFEDR H-mode operation

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【作者】 丁锐刘晓菊王会徐国梁贾国章王福琼司杭桑超峰张晨赵学乐Vincent CHAN

【Author】 Rui DING;Xiaoju LIU;Hui WANG;Guoliang XU;Guozhang JIA;Fuqiong WANG;Hang SI;Chaofeng SANG;Chen ZHANG;Xuele ZHAO;Vincent CHAN;Institute of Plasma Physics, Chinese Academy of Sciences;College of Physics, Donghua University;School of Physics and Optoelectronic Technology, Dalian University of Technology;

【通讯作者】 刘晓菊;

【机构】 Institute of Plasma Physics, Chinese Academy of SciencesCollege of Physics, Donghua UniversitySchool of Physics and Optoelectronic Technology, Dalian University of Technology

【摘要】 A conventional single-null divertor geometry has been proposed for the China Fusion Engineering Demo Reactor(CFEDR). The divertor performance of CFEDR under the conventional high confinement mode(H-mode) scenario with a fusion power of 1.5 GW has been evaluated using the SOLPS-ITER code package. A comparative simulation has been carried out with two different gas puffing settings. The results indicate that simultaneous seeding with both argon(Ar) and deuterium(D) presents a promising solution to divertor power exhaust by increasing radiation losses and thus reducing heat flux. It has been demonstrated that both the inner and outer divertor targets can reach nearly full detachment with total peak heat loads lower than 10 MW m-2 and without notable impurity contamination in the core plasma.The heat loads on both targets contributed by radiation and neutrals are notable for the pronounced divertor detachment scenario. The simulation indicates that, to achieve a similar divertor condition, increasing the D puffing rate can significantly reduce the required Ar puffing rate. This causes a clear reduction in both the average Ar concentration and the effective ion charge number. Additionally, it is found that Ar has a higher compression in the inner divertor region due to the enhanced source-driven flow of recycling main ions in proximity to the outer divertor target. Furthermore, the erosion rate of tungsten divertor targets has been estimated using the DIVIMP code based on the background plasmas provided by SOLPS-ITER. The results indicate that the W erosion rate is generally within the acceptable lifetime requirement for the CFEDR divertor.

【Abstract】 A conventional single-null divertor geometry has been proposed for the China Fusion Engineering Demo Reactor(CFEDR). The divertor performance of CFEDR under the conventional high confinement mode(H-mode) scenario with a fusion power of 1.5 GW has been evaluated using the SOLPS-ITER code package. A comparative simulation has been carried out with two different gas puffing settings. The results indicate that simultaneous seeding with both argon(Ar) and deuterium(D) presents a promising solution to divertor power exhaust by increasing radiation losses and thus reducing heat flux. It has been demonstrated that both the inner and outer divertor targets can reach nearly full detachment with total peak heat loads lower than 10 MW m-2 and without notable impurity contamination in the core plasma.The heat loads on both targets contributed by radiation and neutrals are notable for the pronounced divertor detachment scenario. The simulation indicates that, to achieve a similar divertor condition, increasing the D puffing rate can significantly reduce the required Ar puffing rate. This causes a clear reduction in both the average Ar concentration and the effective ion charge number. Additionally, it is found that Ar has a higher compression in the inner divertor region due to the enhanced source-driven flow of recycling main ions in proximity to the outer divertor target. Furthermore, the erosion rate of tungsten divertor targets has been estimated using the DIVIMP code based on the background plasmas provided by SOLPS-ITER. The results indicate that the W erosion rate is generally within the acceptable lifetime requirement for the CFEDR divertor.

【基金】 supported by National Key Research and Development Program of China (No. 2022YFE0303001);National Natural Science Foundation of China (Nos. 12425509 and 12261131496);the Key Research Program of Frontier Sciences, CAS (No. ZDBS-LY-SLH010);the CASHIPS Director’s Fund (No. BJPY2023A03);the Strategic Priority Research Program of Chinese Academy of Sciences (No. XDB0790103)
  • 【文献出处】 Plasma Science and Technology ,等离子体科学和技术(英文版) , 编辑部邮箱 ,2025年10期
  • 【分类号】TL62
  • 【下载频次】2
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