巻号一覧
後続誌
65 巻 (1991)
- 6 号 p. 601-
- 5 号 p. 489-
- 4 号 p. 399-
- 3 号 p. 289-
- 2 号 p. 115-
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65 巻, 2 号
選択された号の論文の6件中1～6を表示しています
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溝口 忠憲, 下村 安夫1991 年 65 巻 2 号 p. 115-141
発行日: 1991/02/20
公開日: 2010/10/22
ジャーナル フリーEngineering design conditions and constraints regarding with neutron wall load, high heat flux, superconductor magnet, and so on, play important role to design fusion reactors. Present database of first wall materials, high heat flux materials, superconductor etc., are assessed. The impact of these constraints on the next step devices and a first generation of fusion reactor is investigated by the tokamak systems analysis code.抄録全体を表示PDF形式でダウンロード (3122K) -
杉原 正芳, 常松 俊秀1991 年 65 巻 2 号 p. 142-166
発行日: 1991/02/20
公開日: 2010/10/22
ジャーナル フリーPhysics design of ITER and its databases are reviewed. The databases are compiled widely from the data of world wide tokamaks and the related devices. They are presented either in the specialist meetings held during ITER Concept Definition Phase, or reported as contributions for ITER short term R&D during the same phase. Extrapolations of these databases to ITER including modelling studies and their uncertainties are summarised. Physics databases described here comprise the following major physics areas: 1. Energy confinement, 2. Power and particle control, 3. Operation limit and control, 4. Current drive and heating, 5. α-particles and burning plasmas, 6. System studies and operation scenarios.抄録全体を表示PDF形式でダウンロード (3091K) -
多田 栄介, 高津 英幸, 下村 安夫, 本多 力, 黒田 敏公, 吉田 清, 長谷川 満, 杉原 正芳, 柴沼 清, 秋場 真人, 西尾 ...1991 年 65 巻 2 号 p. 167-191
発行日: 1991/02/20
公開日: 2010/10/22
ジャーナル フリーThe major purpose of the International Thermonuclear Experimental Reactor (ITER) is to develop an experimental fusion reactor for the scientific and technological feasibility demonstration of fusion power. ITER Conceptual Design Activites (CDA) began in the spring of 1988 through the united efforts of the European Community, Japan, the Soviet Union and the United States and ended in December 1990. The objectives of this phase were to develop the design of ITER, to perform a safety and environemental analysis, and to define, the future research and development. This paper gives the design concepts developed for the ITER basic devices such as containment structures, remote handling tools, superconducting coils and plasma facing components.抄録全体を表示PDF形式でダウンロード (4758K) -
藤間 一美, 三間 圀興1991 年 65 巻 2 号 p. 192-202
発行日: 1991/02/20
公開日: 2010/10/22
ジャーナル フリーElectronic properties of atoms in high density plasmas are reviewed. Two important features of these plasmas, i.e., pressure ionization and continuum lowering are described in classical theories based on the Debye-Huckel and ion-sphere models. The results of numerical calculations for various model potentials are also summarized. Finally we have looked over recent works on density of state of electron and many-ion-effect in plasmas.抄録全体を表示PDF形式でダウンロード (1269K) -
東辻 浩夫1991 年 65 巻 2 号 p. 203-213
発行日: 1991/02/20
公開日: 2010/10/22
ジャーナル フリーA brief survey is given on ‘Microplasmas’, plasmas with relatively small number of charges of one species confined in the Penning and Paul traps and in the ion storage rings. Methods of confinement and cooling are reviewed and the results of experiments including those of numerical simulations are discussed in relation to the theory of strongly coupled plasmas.抄録全体を表示PDF形式でダウンロード (1365K) -
関 博文, 大崎 博之, 奥山 浩之, 小越 澄雄, 板垣 敏文, 飯田 慶幸, 桂井 誠, 田中 隆, 関口 忠1991 年 65 巻 2 号 p. 214-246
発行日: 1991/02/20
公開日: 2010/10/22
ジャーナル フリーAn l=2, m=12 modular-coil heliotron/torsatron device, SHATLET-M, has been filled with plasmas produced by the irradiation of an intense pulsed CO2 laser beam on a tiny freefalling deutrium pellet. Plasma parameters, namely, line-integrated density, spatially averaged beta value, their decay constants, and plasma currents are measured. The size of the deutrium pellets is in typical cases 0.2mm in diameter and 1mm in length. The pellets are irradiated by a CO2 laser pulse with a total energy of about 300J and a pulse width of 1μs. Within 10 μs, a toroidal plasma is rapidly formed that has a small ititial toroidal plasma current with a peak value of less than 150A. This initial toroidal current is rapidly damped in about 20μs leaving a net-currentfree toroidal plasma for another 200-400 μs. The diamagnetic loop measurement shows that the initial peak value of spatially averaged beta which may contain non-thermal components ranges from 3 to 6%, where the average densety is about 1×1013cm-3. The density increases in proportion to B1.8±0.2 (B is the magnetic field strength.), and the maximum averaged beta increases about in proportion to B. The decay time constants of the averaged beta values are less than about 100μs and no disruptive instability has been observed within these periods.抄録全体を表示PDF形式でダウンロード (3455K)
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