Title of article
Design activities on helical DEMO reactor FFHR-d1
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 ,
Issue Information
روزنامه با شماره پیاپی سال 2012
Pages
9
From page
594
To page
602
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
Journal title
Fusion Engineering and Design
Serial Year
2012
Journal title
Fusion Engineering and Design
Record number
2359362
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