Author/Authors :
Sagara، نويسنده , , A. and Goto، نويسنده , , T. and Miyazawa، نويسنده , , J. and Yanagi، نويسنده , , N. and Tanaka، نويسنده , , T. and Tamura، نويسنده , , H. and Sakamoto، نويسنده , , R. and Tanaka، نويسنده , , M. and Tsumori، نويسنده , , K. and Mitarai، نويسنده , , O. and Imagawa، نويسنده , , S. and Muroga، نويسنده , , T.، نويسنده ,
Abstract :
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.
Keywords :
superconducting magnet , Fueling , Helical , neutronics , reactor design , Liquid blanket
