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AbstractAbstract
[en] Accidents are considered consisting in a breach in the vacuum wall of a fusion reactor, the ingress of air into the torus and the mobilization and expulsion of activated eroded-sputtered material. Previous evaluations on NET, assuming bare plasma-facing components, have been reviewed and new estimates of the rate of material discharge and of the total fraction of discharged material are calculated, including resettlement processes. The case of graphite-tiled walls, without and with combustion, is also examined. Radiological evaluations are then performed to assess the hazard posed by the discharged material both within the NET building and outside it. (author). 14 refs.; 4 figs.; 3 tabs
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Source
Ingen, A.M. van; Nijsen-Vis, A. (Associatie Euratom-FOM, Nieuwegein (Netherlands). FOM-Instituut voor Plasmafysica); Klippel, H.T. (Netherlands Energy Research Foundation, Petten (Netherlands)) (eds.); 937 p; ISBN 0 444 87369 4;
; 1989; p. 1731-1739; North-Holland; Amsterdam (Netherlands); 15. Symposium on fusion technology; Utrecht (Netherlands); 19-23 Sep 1988

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AbstractAbstract
[en] The models used to predict the operational regime and to design the main components of low aspect ratio tokamaks are described. These models have been applied to develop the conceptual design of the TBR-E experiment. (author). 11 refs, 8 figs
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Sociedade Brasileira de Fisica, Sao Paulo, SP (Brazil); 123 p; 1991; p. 332-345; 1. Brazilian Congress on Plasma Physics; Santos, SP (Brazil); 10-13 Dec 1991; Available from the Library of Comissao Nacional de Energia Nuclear, RJ (BR)
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Miscellaneous
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[en] This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project
Original Title
International Thermonuclear Experimental Reactor
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ITER Documentation Series; No. 7; Jan 1990; 119 p
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Miscellaneous
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Progress Report
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AbstractAbstract
[en] This article contains the reply to comments by D.H. McNeill on the article Enhanced Carbon Influx Into TFTR Supershots by A.T. Ramsey, et al.; Nucl. Fusion 31 (1991) 1811
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Journal Article
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AbstractAbstract
[en] Reionization losses in neutral beams for magnetic confinement devices are significant and thus they are an important design consideration. This paper presents an overview of the analyses and data of the past ten years. Included is the traditional analysis, or Classical Effect, which considers the ion source and neutralizer as gas sources; the Culham Effect, which considers gas molecules knocked from walls as a significant additional gas source; and the PLT effect, which suggests wall outgassing is a significant additional gas source
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6. conference on application of accelerators in research and industry; Denton, TX (USA); 3-5 Nov 1980; CONF-801111--
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Journal Article
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IEEE Transactions on Nuclear Science; ISSN 0018-9499;
; v. NS-28(2); p. 1323-1325

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AbstractAbstract
[en] A Compact Torus (CT) is a low-aspect-ratio, axisymmetric, closed-magnetic-field-line configuration with no vessel wall or magnetic field coils linking the hole in the plasma toroid. The potential reactor advantages include high beta, simple geometry, high power density, and translation of the toroid. FRC (Field Reversed Configuration) have negligible toroidal magnetic fields; equilibria tend to be elongated. Gross stability is observed for several Alfven times, but transport mechanisms and confinement time scaling are poorly understood. Translation experiments are expanding the accessable parameter space. Spheromaks have comparable toroidal and poloidal fields. The configuration is related to the RFP although the toroidal field is generated by internal plasma currents. Detached mode (plasma and gun or flux core not connected) and linked mode have been studied. Rotamaks use a rotating magnetic field to maintain the plasma toroidal current; the drive mechanism is analagous to an induction motor. There has been no evidence for gross instabilities although temperatures are low. Particle rings generate CT with particle gyroradii comparable to plasma dimensions. The large orbits may aid in gross MHD stability
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Journal Article
Journal
Nuclear Fusion; ISSN 0029-5515;
; v. 25(8); p. 987-992

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Hiraoka, Toru; Mori, Sigeru; Yamamoto, Kenzo
Proceedings of the 9. Symposium on fusion technology1976
Proceedings of the 9. Symposium on fusion technology1976
AbstractAbstract
[en] A description of thermonuclear devices in operation or under construction in Japan is given. Japanese thermonuclear research programs are presented. Technological problems encountered in the construction of fusion reactors are dealt with. (21 references)
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Commission of the European Communities, Brussels (Belgium); p. 1-20; ISBN 0 08 021369 3;
; 1976; 9. Symposium on fusion technology; Garmisch-Partenkirchen, Germany, F.R; 14 - 18 Jun 1976; Published by Pergamon Press

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AbstractAbstract
[en] Control and data acquisition systems on fusion experiments are a special type of real-time systems combining general process control and monitoring activities with handling bursts of large quantities of data. They are usually designed as distributed systems in which computer communication is of great importance. Among the different communication techniques, Local Area Networks are the most promising technology. As an example an Ethernet based Local Area Network in the ASDEX data acquisition system is shown. (author)
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Commission of the European Communities, Ispra (Italy). Joint Research Centre; 1695 p; ISBN 0 08 032559 9;
; 1984; v. 2 p. 1217-1222; Pergamon Press; Oxford (UK); Fusion technology 1984 symposium; Varese (Italy); 24-28 Sep 1984

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AbstractAbstract
[en] The lecture given as a memorial to Lev Andreevich Artsimovich provided an overview of fusion, in particular its development to the present, its place in the present world energy and political scenarios, and its future directions. The role played by tokamaks, promoted by Artsimovich, in the development of fusion was highlighted, in particular the successes of JET as an international collaboration, another phenomenon promoted by Artsimovich. The role of the quadripartite ITER project, also to be designed as a tokamak, was reviewed. Political considerations which need to be addressed were enumerated
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International Atomic Energy Agency, Vienna (Austria); Nucl. Fusion; Suppl. 1989; 775 p; ISBN 92-0-130089-1;
; 1989; v. 1 p. 3-8; IAEA; Vienna (Austria); 12. international conference on plasma physics and controlled nuclear fusion research; Nice (France); 12-19 Oct 1988; IAEA-CN--50/A-0

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Book
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Ellis, R. Jr.; Stencel, J.R.
Princeton Univ., NJ (USA). Plasma Physics Lab1984
Princeton Univ., NJ (USA). Plasma Physics Lab1984
AbstractAbstract
[en] The S-1 machine is part of the Magnetic Fusion Program. The goal of the Magnetic Fusion Program is to develop and demonstrate the practical application of fusion. S-1 is an experimental device which will provide an essential link in the research effort aiming at the realization of fusion power
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Feb 1984; 101 p; Available from NTIS, PC A06/MF A01; 1 as DE84010234
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