NIFS-565

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Author(s):

A. Sagara, K.Y. Watanabe, K. Yamazaki, O. Motojima, M. Fujiwara, O. Mitarai, S. Imagawa, H. Yamanishi, H. Chikaraishi, A. Kohyama, H. Matsui, T. Muroga, T. Noda, N. Ohyabu, T. Satow, A.A. Shishkin, S. Tanaka, T. Terai and T. Uda

Title:

LHD-Type Compact Helical Reactors

Date of publication:

Oct. 1998

Key words:

IAEA, fusion energy conference, Yokohama

Abstract:

From the point of view of D-T fusion demonstration reactors, the LHD-type helical reactor designs are studied to clarify design issues for realizing compact reactors, where the major radius R should be as small as possible. The LHD concept is characterized by two advantages; (1) simplified superconducting continuous-coil system and (2) efficient closed helical divertor. Therefore, on the basis of physics and engineering results established in the LHD project, which has already started plasma confinement experiments, two possible approaches on reactor designs are investigated: increasing the toroidal field B_0 in the concept of Force-Free Helical Reactor (FFHR) with a continuous-coil system, and increasing the plasma minor radius a_p in the concept of Modular Heliotron Reactor (MHR) with an effcient closed divertor. Physics and engineering results are presented, including new proposals.

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