巻号一覧
後続誌
66 巻 (1991)
- 6 号 p. 581-
- 5 号 p. 473-
- 4 号 p. 357-
- 3 号 p. 224-
- 2 号 p. 104-
- 1 号 p. 9-
66 巻, 5 号
選択された号の論文の3件中1～3を表示しています
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熊沢 隆平1991 年 66 巻 5 号 p. 473-493
発行日: 1991/11/20
公開日: 2010/10/22
ジャーナル フリーTore Supra has been designed to be operated in long pulse (>30 sec) with high power additional heating (<30 MW). The main issue is to control the plasma density and impurity accumulation in high density and temperature plasma regime. The long pulse discharges have been operated at the nominal plasma current and steady-state toroidal magnetic field. A multi-pellets injector could successfully maintain a 4 ×1019m3 quasistationary density with up to 25 pellets. Lower hybrid waves with power up to 3.8 MW have been launched driving up to 50 % of the total current with 22 sec operation. Modification of plasma boundary conditions by a pump limiter and an ergodic divertor (ED) has been investigated. Particularly ED can change the transport in the edge plasma and reduce the impurity influx.抄録全体を表示PDF形式でダウンロード (2128K) -
安積 正史, 若谷 誠宏1991 年 66 巻 5 号 p. 494-524
発行日: 1991/11/20
公開日: 2010/10/22
ジャーナル フリーIn this section, basic properties of plasma stabilities in toroidal systems are described. MHD stability with spatially large scale is analyzed by using the linearized MHD equations. A variety of instabilites are excited by free energy sources of the magnetic energy and the internal energy. Key instabilities limiting the plasma current and pressure are depend on the magnetic confugulation, since characteristics of magnetic field such as the curvature of field line and the safety factor (or, the rotational transform) are different; ballooning mode is important in a tokamak plasma, while interchange one is the limiting factor in RFP and helical plasmas. Instabilities excited by the finite electric resistivity and high energy ions are also described. Drift wave instabilities with small spatial scale of order of larmor radius also show new feature in a toroidal system. Stability of trapped electron mode and ion temperature gradient mode is described. And the basic formulation of edge turbulence is presented.抄録全体を表示PDF形式でダウンロード (3347K) -
Nobuyoshi Ohyabu1991 年 66 巻 5 号 p. 525-531
発行日: 1991/11/20
公開日: 2010/10/22
ジャーナル フリーHigh temperature divertor plasma operation has been proposed, which is expected to enhance the core energy confinement and eliminates the heat removal problem of a reactor grade device. In this approach, the heat flux is guided through divertor channels to remote areas with large target surface, to reduce the heat load on the target plate substantially. This allows pumping of the particles recycled at the target plate and hence maintaining of h igh divertorplasma temperature, comparable to the core temperature. The energy confinement is then determined by the diffusion coefficient of the core plasma.抄録全体を表示PDF形式でダウンロード (929K)
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