All issues
Successor
Volume 65 (1991)
- Issue 6 Pages 601-
- Issue 5 Pages 489-
- Issue 4 Pages 399-
- Issue 3 Pages 289-
- Issue 2 Pages 115-
- Issue 1 Pages 5-
Volume 65, Issue 2
Displaying 1-6 of 6 articles from this issue
- |<
- <
- 1
- >
- >|
-
Tadanori Mizoguchi, Yasuo Shimomura1991 Volume 65 Issue 2 Pages 115-141
Published: February 20, 1991
Released on J-STAGE: October 22, 2010
JOURNAL FREE ACCESSEngineering 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.View full abstractDownload PDF (3122K) -
Masayoshi Sugihara, Toshihide Tsunematsu1991 Volume 65 Issue 2 Pages 142-166
Published: February 20, 1991
Released on J-STAGE: October 22, 2010
JOURNAL FREE ACCESSPhysics 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.View full abstractDownload PDF (3091K) -
Eisuke Tada, Hideyuki Takatsu, Yasuo Shimomura, Tutomu Honda, Toshimas ...1991 Volume 65 Issue 2 Pages 167-191
Published: February 20, 1991
Released on J-STAGE: October 22, 2010
JOURNAL FREE ACCESSThe 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.View full abstractDownload PDF (4758K) -
Kazumi Fujima, Kunioki Mima1991 Volume 65 Issue 2 Pages 192-202
Published: February 20, 1991
Released on J-STAGE: October 22, 2010
JOURNAL FREE ACCESSElectronic 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.View full abstractDownload PDF (1269K) -
Hiroo Totsuji1991 Volume 65 Issue 2 Pages 203-213
Published: February 20, 1991
Released on J-STAGE: October 22, 2010
JOURNAL FREE ACCESSA 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.View full abstractDownload PDF (1365K) -
Hirofumi Seki, Hiroyuki Ohsaki, Hiroyuki Okuyama, Sumio Kogoshi, Toshi ...1991 Volume 65 Issue 2 Pages 214-246
Published: February 20, 1991
Released on J-STAGE: October 22, 2010
JOURNAL FREE ACCESSAn 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.View full abstractDownload PDF (3455K)
- |<
- <
- 1
- >
- >|