巻号一覧
後続誌
64 巻 (1990)
- 6 号 p. 461-
- 5 号 p. 397-
- 4 号 p. 335-
- 3 号 p. 255-
- 2 号 p. 144-
- 1 号 p. 5-
64 巻, 3 号
選択された号の論文の5件中1～5を表示しています
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滝塚 知典1990 年 64 巻 3 号 p. 255-280
発行日: 1990/09/20
公開日: 2010/10/22
ジャーナル フリーA poloidal divertor system is available for the thermonuclear fusion experimental tokamak reactor from the viewpoint of power and particle control. Divertor plasma models are reviewed briefly, which are used for analyzing divertor functions and for computer simulations. Simple results of one-dimensional analysis parallel to magnetic field lines are given, which show the qualitative characteristics of divertor plasma and rough values of divertor-plasma parameters. In relation to the boundary condition at the divertor plate, sheath conditions are especially noted in the appendix. Experimental results of density and temperature profiles in divertor plasmas as well as the width of heat flux are reviewed. Results of impurity shielding experiments and He ash exhaust experiments are also described shortly. Comment on the completion of divertor-plasma database is attached finally.抄録全体を表示PDF形式でダウンロード (3107K) -
関 昌弘1990 年 64 巻 3 号 p. 281-290
発行日: 1990/09/20
公開日: 2010/10/22
ジャーナル フリーPlasma facing materials are subjected to intense heat load in both normal and off-normal operations. Carbon based materials especially carbon fiber composites with high thermal conductivity are employed as the plasma facing material in next step machines like ITER. Design analysis on ITER divertor plates shows that thermal shock erosion of carbon based materials limits life-time of the divertor, leading to extensive experimental studies to investigate the erosion due to intense thermal shock at disruptions. The present paper outlooks the recent results on laboratory experiments on the thermal shock erosion of both carbon materials and metals.抄録全体を表示PDF形式でダウンロード (1575K) -
和久田 義久, 江本 信也, 中島 秀紀, 中尾 安幸, 本多 琢朗, 本多 義則1990 年 64 巻 3 号 p. 291-304
発行日: 1990/09/20
公開日: 2010/10/22
ジャーナル フリーThe use of parallel spin-polarized DT or D3He fuel increases the fusion cross-section by 50%. By implosion-burn simulation for inertially confined fusion (ICF) pellets of the spin-polarized fuels, we found that the input energy requirement could be reduced by nearly a fact of two. These pellets taken up here include large-high-aspect-ratio DT target proposed in ILE Osaka University and DT ignitor/D3He fuel pellet proposed by our group. We also found that the polarized state could survive during the implosion-burn phase.抄録全体を表示PDF形式でダウンロード (1536K) -
Tihiro Ohkawa1990 年 64 巻 3 号 p. 305-314
発行日: 1990/09/20
公開日: 2010/10/22
ジャーナル フリーThe concept of a thermal dike for the reduction of electron heat loss parallel to the magnetic field from magnetically confined plasma to the material wall or divertor plates is discussed. The ponderomotive pressure of the rf field or the combination of the magnetic mirror and rf heating pushes the cold plasma towards the divertor plate. The influx of cold electrons is prevented by a thermal dike and the parallel heat loss which takes the form of exchange between hot and cold electrons in the long mean free path regime is reduced抄録全体を表示PDF形式でダウンロード (1360K) -
横倉 賢治, 沢畠 正之, 佐藤 稔, 日下 誠, 藤城 賢司, 本田 正男, 前原 直, 高橋 春次, 関 正美, 池田 佳隆, 上原 和 ...1990 年 64 巻 3 号 p. 315-326
発行日: 1990/09/20
公開日: 2010/10/22
ジャーナル フリーOperational experience and improvement of klystrons for the JT-60 LHRF heating system are reported. JT-60 klystron is the most powerful and wide band one forfusion plasma heating. Operational experience of these klystrons were accumulated after encountering many troubles to be removed and the stable operation is performed to repair the electron gun in the klystron. These are reported acompanying the data in detail.抄録全体を表示PDF形式でダウンロード (2641K)
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