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基于TSC的CFETR偏滤器靶板热流数值模拟

Simulation of Target Plate Heat Flux of CFETR Divertor Based on TSC
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摘要 位形放电,在程序中添加偏滤器靶板,最外封闭磁面以外的等离子体沿磁力线打到偏滤器靶板上。模拟得到了两种偏滤器位形放电下的靶板热流,重点分析了平顶阶段偏滤器靶板热流分布情况,对下单零偏滤器位形和准雪花偏滤器位形的热流进行了比较。结果表明热流在等离子体电流爬升阶段基本上小于1 MW/m2,在平顶阶段准雪花偏滤器热流峰值为23.34 MW/m2,下单零偏滤器热流峰值为39 MW/m2,准雪花偏滤器靶板热流小于下单零偏滤器。计算结果为下一步热结构多物理场耦合分析提供了热源分布,对CFETR的工程设计具有一定的参考价值。 In order to obtain the heat flux distribution of CFETR divertor target plate, TSC (Tokamak Simula-tion Code) program is used to simulate the configuration discharge of Lower Single Null and Quasi- Snowflake divertor of CFETR. The divertor target plate is added to the program, and the plasma outside the outermost enclosed magnetic surface hits the divertor target plate along the magnetic force line. The heat flux of the target plate under the discharge of the two divertor configurations is simulated. The heat flux distribution of the divertor target plate in the flat-top stages is analyzed, and the heat flux of the Lower Single Null divertor configuration and the Quasi-Snowflake divertor configuration are compared. The results show that the heat flow is basically less than 1MW/m2 in the plasma current climbing stage. In the flat-top stage, the peak heat flux of the Quasi-Snowflake divertor configuration is 23.34 MW/m2, the peak heat flux of the Lower Single Null divertor config-uration is 39 MW/m2, and the target heat flux of the Quasi-Snowflake divertor is less than that of the Lower Single Null divertor. The calculation results provide the heat source distribution for the multi physical field coupling analysis of thermal structure in the next step, and have a certain ref-erence value for the engineering design of CFETR.
出处 《核科学与技术》 2022年第2期103-115,共13页 Nuclear Science and Technology
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