Design activities on helical DEMO reactor FFHR-d1 |
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Authors: | A. Sagara T. Goto J. Miyazawa N. Yanagi T. Tanaka H. Tamura R. Sakamoto M. Tanaka K. Tsumori O. Mitarai S. Imagawa T. Muroga |
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Affiliation: | 1. National Institute for Fusion Science, Toki, Gifu 509-5292, Japan;2. Tokai University, 9-1-1 Toroku, Kumamoto 862-8652, Japan |
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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. |
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