CFETR电流爬升阶段中性束注入伏秒数分析  

Discharge simulation and volt-second consumption analysis of neutral beam injection on CFETR

作　　者：陆野 杨锦宏 桂腾 任珍珍 刘胜 宁洪伟 徐敬坤 宋强 邓海飞 汪卫华 LU Ye;YANG Jin-hong;GUI Teng;REN Zhen-zhen;LIU Sheng;NING Hong-wei;XU Jing-kun;SONG Qiang;DENG Hai-fei;WANG Wei-hua(Institutes of Physical Science and Information Technology,Anhui University,Hefei 230039;School of Computer Science and Technology,Anhui University,Hefei 230601;School of Physics and Materials Science,Anhui University,Hefei 230601;PLA Army Academy of Artillery and Air Defense,Hefei 230031)

机构地区：[1]安徽大学物质科学与信息技术研究院,合肥230039 [2]安徽大学计算机科学与技术学院,合肥230601 [3]安徽大学物理与材料科学学院,合肥230601 [4]陆军炮兵防空兵学院,合肥230031

出　　处：《核聚变与等离子体物理》2022年第3期354-360,共7页Nuclear Fusion and Plasma Physics

基　　金：国家自然科学基金(11975022);国家重点研发计划(2018YFE0309100,2017YFE0300603,2018YFE0310400);安徽省自然科学基金(1908085MA26,2008085QA37)

摘　　要：利用随时间演化的自由边界轴对称托卡马克代码(TSC)对中国聚变工程实验堆(CFETR)电流爬升阶段的放电进行数值模拟,给出了主要的等离子体参数、等离子体位形演化和线圈电流演化,分析了等离子体电流在中性束粒子辅助加热(NBI)和无辅助加热条件下CFETR电流爬升过程的伏秒数消耗,以及不同的中性束注入条件下的影响。结果表明,适当控制中性束粒子的注入时间及能量沉积剖面可以节省伏秒数消耗10%~25%左右。模拟结果对CFETR的工程设计具有一定的参考价值。The free boundary axisymmetric tokamak code(TSC)evolving with time is used to numerically simulate the discharge in the current ramping stage of China fusion engineering experimental reactor(CFETR),and the main plasma parameters,plasma configuration and coil current evolutions are given.The volt second consumption of plasma current in the ramping process of CFETR current under the conditions of neutral beam injection(NBI)assisted heating and no auxiliary heating,and the effects of different neutral beam injection conditions are analyzed.The results show that about 10%-25%volt seconds can be saved by properly controlling the injection time and energy deposition profile of neutral beam particles.The simulation results have certain reference value for the engineering design of CFETR.

关 键 词：TSC 中国聚变工程实验堆 中性束注入 放电模拟 伏秒数消耗 

分 类 号：TL622[核科学技术—核技术及应用]