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矢木 雅敏; 松山 顕之; 若狭 有光*; 奴賀 秀男
no journal, ,
The runaway electron (RE) confinement has been investigated by a relativistic guiding-center trace code ETC-Rel using analytic expressions of the MHD modes. In this work, the nonlinear evolution of the MHD field is simulated by the 4-field reduced MHD code R4F. The use of nonlinear MHD codes allows us to treat more realistic values of the saturated amplitude and the eigenmode structure for given equilibrium. Results of the code verification for R4F, which simulates nonlinear coupling of the (2, 1) and (3, 2) tearing modes are shown. The RE confinement using nonlinear MHD simulations of density-limit disruptions with the edge radiation loss is also discussed.
小関 隆久; Clement, L. S.*; 中島 徳嘉*
no journal, ,
ITER Remote Experimentation Centre (REC) based on the Broader Approach (BA) activity of the joint program of Japan and Europe (EU) is being built in Rokkasho, Japan. The REC will make possible to participate the ITER experiment remotely from Rokkasho. It will have the functions of the remote experiment system, such as setting of experiment parameters, shot scheduling, real time data streaming, communication by video-conference between the remote-site and on-site. Also, it has a function of numerical simulation for preparation and estimation of the shot performance and the analysis of the plasma shot. In order to make effective use of the limited machine time, it is important to improve the environment for the shot preparation and the data analyses. This can be performed by detailed data analysis and more efficient plasma performance prediction by the simulation. The role of the simulation on the experiments and the future function for DEMO are discussed.
瀬戸 春樹; 福山 淳*
no journal, ,
A new framework of core-edge-SOL transport simulation has been proposed. In this work, a set of transport equations applicable on both core and SOL region is formulated and a concept of a numerical scheme connecting 2D transport code and 2D equilibrium code is also proposed. This system allows us to simulate core-edge-SOL transport without computational boundary in the edge region. The proposed equation system is equivalent to conventional 1D core transport model in the weakly collisional limit and to conventional 2D SOL transport model in the strongly collisional limit.
仲田 資季; 本多 充; 吉田 麻衣子; 浦野 創; 前山 伸也; 沼波 政倫*; 渡邉 智彦*
no journal, ,
ITERやDEMOに代表される次世代の燃焼プラズマの乱流輸送特性の解明と予測には、核融合プラズマの第一原理モデルであるジャイロ運動論に基づいた乱流輸送シミュレーションが不可欠である。本研究では、著者らが開発している第一原理乱流シミュレーションコードGKV-Jを駆使して、実際のJT-60Uトカマク平衡を用いたITG-TEM駆動乱流輸送シミュレーションを実現した。まず、微視的線形安定性解析により、プラズマ内側領域ではITGモード、中間領域ではITG-TEMモード、外側領域ではTEMモードが支配的となることを同定した。次に非線形乱流輸送シミュレーションを実施し、GKV-Jのシミュレーション結果が従来の流体輸送モデルでは定量性を著しく欠いていた領域に対しても、イオン/電子熱輸送レベルに関する実験結果をよく再現することを確認した。また、詳細な乱流データの解析により、イオン/電子熱輸送、粒子輸送といったそれぞれの輸送チャンネルに対して異なる乱流/ゾーナルフロー強度の依存性が存在することが明らかになった。