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Farfaletti-Casali, F.; Nishio, S.; Reynolds, P.
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. N1983
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. N1983
AbstractAbstract
[en] The paper defines the Phase II INTOR configuration that has evolved during this conceptual design period and represents the combined efforts of all participating countries: USSR, Japan, Europe, and the USA. As a result of the new concepts developed in this phase, a new design configuration has evolved, using the same number of TF coils (12), yet permitting a reduction in the coil size by approximately 15%. The associated magnetic ripple for this design has increased slightly to approximately 0.9%. Due to the strong influence of TF coil size on the other tokamak systems such as PF coils, power supplies and machine structure, the overall cost of the INTOR project may be reduced by over 10%. The revised design incorporates several major changes from the previous design related to the vacuum topology, the torus, and the structural design. The configuration also provides sufficient flexibility to accommodate the uncertainty involved in the choice of bulk heating and impurity control methods; i.e., neutral beam injection or ICRF for heating and a poloidal divertor or pumped limiter located at the bottom of the plasma chamber for impurity control. The Phase II configuration is not fully optimized for either the limiter or divertor impurity control systems; however, the solution developed has been useful in this conceptual design phase to design and evaluate the many components associated with a tokamak device, i.e., TF coils, breeding blankets, heating systems, etc. (orig./HP)
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Commission of the European Communities, Luxembourg; Argonne National Lab., IL (USA); 181 p; ISBN 0444 86702 3;
; 1983; p. 9-15; North-Holland; Amsterdam (Netherlands); 7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7); Chicago, IL (USA); 22-26 Aug 1983; CONTRACT W-76405-ENG-26

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No abstract available
Original Title
Caracterisation de la turbulence magnetique sur TCA
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Spring meeting of the Swiss Physical Society; Fribourg (Switzerland); 24-25 Mar 1983; Published in summary form only.
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Journal Article
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Helvetica Physica Acta; ISSN 0018-0238;
; v. 56(4); p. 951

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[en] This paper describes an unconventional approach to fusion in which the principal operations on the plasma, namely heating it to fusion temperature and extracting the /CHI/-particle energy, are performed mechanically by means of a rotationally-stabilized liquid lithium liner. This concept may properly be described as a fusion engine, except there is no shaft output; all the fusion energy appears in the liner as heat. Although the plasma is magnetically confined there are no external magnet coils; the method of plasma production by electron beams also creates the confining magnetic fields which are maintained by induced currents in the plasma and on the liner surface. Apart from the obvious economy of eliminating superconducting coils, this also allows the reactor to be built from ferritic steel. The basic simplicity of the Linus concept is due to the combination in one element, the liner, of functions which in other fusion concepts require separate systems. It is the confining field coil, the plasma heater, the first wall, the tritium breeding blanket, the heat transfer medium and the main vacuum pump. Perhaps its most important function is that of providing a continuously regenerated liquid first wall whose mean power loading can greatly exceed the limits of a solid first wall
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Source
Brunelli, B; p. 257-279; 1982; p. 257-279; Plenum Pub. Corp; New York, NY (USA); International school of fusion reactor technology's course on unconventional approaches to fusion; Erice (Italy); 16-27 Mar 1981
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[en] Until recently the realization of a D-3 He or a D-D burning reactor had been considered a goal to be achieved in the next century, since a near-term experiment to test the possibility of igniting these kinds of plasmas could not be foreseen. However, recent experimental observations, as well as new theoretical developments, have led to the identification of a class of experiments that can lead to the realization of ignition conditions for a D-3 He system on the basis of present-day technology. This paper discusses how this goal may be achieved by specifying the requisite plasma confinement configuration, which can be achieved in an axisymmetric toroidal configuration, embodied in a device identified previously as ''Katharsor'' or ''candor''. The technological feasibility of these experimental reactors are discussed as is a description of the main parameters of two reference devices. In addition, the perspective characteristics of high-field, high particle-density D-3 He power producing reactors are examined
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Source
Brunelli, B; p. 417-437; 1982; p. 417-437; Plenum Pub. Corp; New York, NY (USA); International school of fusion reactor technology's course on unconventional approaches to fusion; Erice (Italy); 16-27 Mar 1981
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[en] The RIGGATRON fusion power core, patented by INESCO Inc, is applicable to a wide variety of energy plant types. Demonstration testing of five full scale RIGGATRON fusion power units is underway. A tokamak confines a hot plasma in a toroidal magnetic bottle, as shown. Because it is a canned assembly, it is easily replaced. There is no meltdown scenario, and fusion is environmentally benign. The first plants are expected to come on line in the 1990's. Projected ROI may exceed 100% per year. As RIGGATRON becomes available, a rapid displacement of conventional plants is projected
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10. energy technology conference; Washington, DC (USA); 28 Feb - 2 Mar 1983; CONF-830213--
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Journal Article
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Conference
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Energy Technology (Washington, D.C.); ISSN 0161-6048;
; v. 10 p. 1209-1218

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[en] The interface system to transfer the signal from the TRIAM-1 tokamak device to a data processing system is described. The data processing system is consists of a computer HITAC - 10 II/L and peripheral equipments. The plasma current, the loop voltage, the plasma position, MHD oscillation, the toroidal field, the vertical field, electron density, filling pressure, electron temperature and ion temperature are analyzed by the system. AD converters, and the amplification and transmission circuits for the signals concerning these quantities were designed and manufactured. By using the system, it is possible to analyze large amount of the data obtained by one-shot experiment. (Kato, T.)
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Journal Article
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Oyo Rikigaku Kenkyusho Shoho; ISSN 0030-7734;
; (no.57); p. 315-331

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[en] Progress is reported by a number of contributors towards the first power producing fusion device. The current state of research on different concepts towards achieving this goal is outlined. (U.K.)
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1981; 90 p; Pergamon Press Inc; New York (USA); ISBN 0-08-028046-3; 

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[en] The paper summarizes the development of the JET (Joint European Torus) programme, from the early days of plasma research in the 1930's, to the present day performance of JET. JET aims to produce a study plasma, in conditions, and with dimensions, approaching those needed in a fusion reactor. Euratom, containment of the high temperature plasma, tokamak configuration and fusion work in Japan, Russia and the United States are all briefly discussed. (U.K.)
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Journal Article
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Atom (London); ISSN 0004-7015;
; (no.332); p. 3-5

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[en] A description is given of the construction of the Joint European Torus at Culham, England. Following an outline of the principles of fusion reactions, the advanced engineering and welding techniques used in building the tokamak device are discussed. (UK)
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Journal Article
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Metal Construction; ISSN 0307-7896;
; v. 15(4); p. 195-198

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ALLOYS, ALUMINIUM ADDITIONS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CLOSED PLASMA DEVICES, CORROSION RESISTANT ALLOYS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INCONEL ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, JOINING, JOINTS, MATERIALS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NICKEL BASE ALLOYS, NIOBIUM ALLOYS, SILICON ALLOYS, STAINLESS STEELS, STEELS, THERMONUCLEAR DEVICES, TITANIUM ADDITIONS, TOKAMAK DEVICES
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[en] The aim of nuclear fusion research is to make fusion energy available as a new energy source. Fusion processes occur naturally in the sun, where hydrogen nuclei release energy by combining to form helium. A fusion reactor on earth will require even higher temperatures than in the interior of the sun, and it will be based on deuterium and tritium reactions. JET (Joint European Torus) is a major fusion experiment now under construction near Abingdon in the U.K. It is aimed at producing conditions approximating those necessary in a fusion reactor. The results expected from JET should permit a realistic evaluation of the prospects for fusion power and serve as a basis for the design of the next major fusion experiment. (Auth.)
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4. Nordic meeting on nuclear physics; Fuglsoe (Denmark); 16-20 Aug 1982
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Journal Article
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Conference
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Physica Scripta; ISSN 0031-8949;
; v. T5 p. 136-139

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