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紧凑型聚变裂变混合堆先进运行模式的数值模拟 被引量：3

Simulation on advanced operation mode for the compact fusion-fission hybrid reactor
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摘要 使用Jsolver程序及托卡马克模拟程序TSC对紧凑型聚变裂变混合堆系统的反剪切平衡位形、自举电流份额及放电模拟进行数值模拟研究,以此探讨该混合堆的可行性和先进性。 Reversed shear （RS） operation mode is simulated with Jsolver and TSC codes on some important issues, such as RS Plasma configuration, bootstrap current fraction and RS operation mode discharge simulation etc.. To some degree, the modeling results show that the RS operation mode is advanced and feasible for the compact Fusion-fission hybrid reactor.
作者 陈美霞 刘成岳 吴斌
机构地区 合肥工业大学电子科学与应用物理学院 中国科学院等离子体物理研究所
出处 《核聚变与等离子体物理》 CAS CSCD 北大核心 2012年第4期323-327,共5页 Nuclear Fusion and Plasma Physics
基金 国家自然科学基金资助项目(10975160 11175211) 中央高校基本科研业务费专项资金资助项目(2010HGXJ0078 2010HGBZ0556 2011HGXJ1064)
关键词 紧凑型聚变裂变混合堆 Jsolver 托卡马克模拟程序 放电模拟 Compact fusion-fission hybrid reactor Jsolver rokamak simulation code Discharge simulation
分类号 TL639 [核科学技术—核技术及应用]
  • 相关文献

参考文献10

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二级参考文献19

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共引文献6

同被引文献18

  • 1中国科学院等离子体物理研究所.EAST装置设计文集[Z].北京:中国科学院等离子体物理研究所,1999.
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  • 3中国科学院等离子体物理研究所.EAST中性束注入系统物理方案[R].北京:中国科学院等离子体物理研究所,2008.
  • 4Jardin S, Pomphrey N, De Lucia J. Dynamic modeling of transport and positional control of tokamaks [J]. J Comput Phys, 1986,66(2) :481--507.
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  • 7Wu B, Wang J, Li J,et al. Neutral beam injection simulation of EAST [J]. Fusion Eng Des, 2011, 86 (6/7/ 8) :947--950.
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  • 9Jardin S, Pomphrey N, De Lucia J. Dynamic modeling of transport and positional control of tokamaks [J]. J Comput Phys, 1986,66(2) :481--507.
  • 10Jardin S, Kessel C E, Pomplrey N. Poloidal flux linkage requirements for the ITER [J].Nuclear Fusion 1994,34(8): 1145--1160.

引证文献3

二级引证文献2

核聚变与等离子体物理
2012年 第4期

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