Design activities on helical DEMO reactor FFHR-d1

作者：Sagara A^*; Goto T; Miyazawa J; Yanagi N; Tanaka T; Tamura H; Sakamoto R; Tanaka M; Tsumori K; Mitarai O; Imagawa S; Muroga T

来源：Fusion Engineering and Design, 2012, 87(5-6): 594-602.

DOI：10.1016/j.fusengdes.2012.01.030

• Helical
• Reactor design
• Neutronics
• Liquid blanket
• Superconducting magnet
• Fueling

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%26D 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.

• 出版日期2012-8