Design activities on helical DEMO reactor FFHR-d1
Design activities on helical DEMO reactor FFHR-d1
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DOI：
10.1016/j.fusengdes.2012.01.030
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发表时间：
2012-08
影响因子：
1.7
通讯作者：
A. Sagara;T. Goto;J. Miyazawa;N. Yanagi;Teruya Tanaka;H. Tamura;R. Sakamoto;Masahiro Tanaka;K. Tsumori;O. Mitarai;S. Imagawa;T. Muroga
中科院分区：
文献类型：
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作者：
A. Sagara;T. Goto;J. Miyazawa;N. Yanagi;Teruya Tanaka;H. Tamura;R. Sakamoto;Masahiro Tanaka;K. Tsumori;O. Mitarai;S. Imagawa;T. Muroga
Based on high-density and high-temperature plasma experiments in the large helical device (LHD), conceptual design studies of the LHD-type helical DEMO reactor FFHR-d1 have been conducted by integrating wide-ranged R&D activities on core plasmas and reactor technologies through cooperative researches under the fusion engineering research project, which has been launched newly in NIFS. Current activities for the FFHR-d1 in this project are presented on design window analyses with designs on core plasma, neutronics for liquid blankets, continuous helical magnets, pellet fueling, tritium systems and plasma heating devices.
