A Conceptual Design of Superconducting Spherical Tokamak Reactor

カテゴリ: 論文誌(論文単位)

グループ名: 【A】基礎・材料・共通部門

発行日: 2012/07/01

タイトル(英語): A Conceptual Design of Superconducting Spherical Tokamak Reactor

著者名: Yoshio Nagayama (National Institute for Fusion Sicence), Kichiro Shinya (Toshiba Engineering Service Corp), Yasutoshi Tanaka (Nagoya Institute of Technology)

著者名(英語): Yoshio Nagayama (National Institute for Fusion Sicence), Kichiro Shinya (Toshiba Engineering Service Corp), Yasutoshi Tanaka (Nagoya Institute of Technology)

キーワード: ST，reactor，design，superconductor，steady state，high beta

要約(英語): This paper presents a fusion reactor concept named "JUST (Japanese Universities' Super Tokamak reactor)". From the plasma confinement system to the power generation system is evaluated in this work. JUST design has features as follows: the superconducting magnet, the steady state operation with high bootstrap current fraction, the easy replacement of neutron damaged first wall, the high heat flux in the divertor, and the low cost (or high β). By winding the OH solenoid over the center stack of toroidal field coil, we have the low aspect ratio and the 80cm thick neutron shield to protect the superconducting center stack. JUST is designed by using the 0-D transport code under the assumption that the energy confinement time is 1.8 times of the IPB98(y,2) scaling. Main parameters are as follows: the major radius of 4.5m, the aspect ratio of 1.8, the elongation ratio of 2.5, the toroidal field of 2.36T, the plasma current of 18MA, the toroidal beta of 22%, the central electron and ion temperature of 15keV and the fusion thermal power of 2.4GW. By using the mercury heat exchanger and the steam turbine, the heat efficiency is 33% and the electric power is 0.74GW.

本誌: 電気学会論文誌A（基礎・材料・共通部門誌） Vol.132 No.7 （2012） 特集：The 16th International Workshop on Spherical Tori 2011

本誌掲載ページ: 555-566 p

原稿種別: 論文／英語

電子版へのリンク: https://www.jstage.jst.go.jp/article/ieejfms/132/7/132_555/_article/-char/ja/