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AbstractAbstract
[en] The purpose of the fusion programme is to provide broadly competitive electricity (with perhaps credit given for possible environmental, diversity and safety benefits). Fusion reactor design studies routinely predict electricity prices broadly comparable to conventional alternatives such as the PWR, despite the devices producing the electricity being typically ∝10 times bigger, more complicated and requiring more maintenance. In this paper this issue is considered. These low power densities, indicated both by reactor studies and confirmed by generic engineering and geometric arguments, are shown to be a rather fundamental feature of the D-T tokamak. Coupled with the complex construction and expensive materials required, and the probable low availability its serial complexity and high maintenance needs will cause, it is argued that D-T tokamak electricity prices will be a significant multiple of alternatives. This is the case even with all remaining physics issues assumed resolved successfully. (orig.)
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19. symposium on fusion technology (SOFT-19); Lisbon (Portugal); 16-20 Sep 1996
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[en] The Effective Management Method is an action decision manner to work out the strategy of enterprises, which was developed in Japan on the base of the Kepner and Trigoe Method developed in the USA. The authors applied this method with a small modification to a burn cycle study of tokamak power plants. The numerical figure of merit for the pulsed and steady state operations are visually shown. Steady state, 1 hour pulse (with and without energy reservoir) and half-day long pulse reactor are compared. The EM method provides a common base for such comparing study. The highest score is given to an 1 hour pulsed operated reactor with an energy reservoir for the continuous electric output. However it is also pointed out that there is no 'significant' superiority in both of the steady state and pulse reactors. (author)
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[en] Deuterium and tritium are the components of the thermonuclear fusion fuel. Deuterium is very common on earth and tritium will be produced in the fusion device itself by the collision of fast neutrons emitted in fusion reactions on lithium targets. Thermonuclear fusion will be a revolution as it will be an unlimited and massive energy source that will certainly open the way to other uses like fueling planes and ships or accelerating spatial flights than electricity production only. (A.C.)
Original Title
La fusion nucleaire, un nouveau paradigme?
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2 refs.
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AbstractAbstract
No abstract available
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Anon; p. 64; 1976; 9. symposium on fusion technology; Garmisch-Partenkirchen, F.R. Germany; 14 Jun 1976; AED-CONF--76-309-062; Short communication only. Available from ZAED.
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[en] The Ignitor experiment is the first to have been proposed and designed with the purpose of studying the conditions under which ignition in D-T plasmas can be attained. The design of the machine has kept pace with the evolution of the physics of magnetically confined plasmas as well with progress made in the design of other advanced confinement experiments
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Archundria, C.
Proceedings of the 5. symposium on nuclear chemistry, radiochemistry and radiation chemistry, meeting room of the University of Guanajuato, Mexico, 4-7 December 19841984
Proceedings of the 5. symposium on nuclear chemistry, radiochemistry and radiation chemistry, meeting room of the University of Guanajuato, Mexico, 4-7 December 19841984
AbstractAbstract
No abstract available
Original Title
El tritio, un radionuclido en importancia mundial
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Instituto Nacional de Investigaciones Nucleares, Mexico City; Universidad Nacional Autonoma de Mexico, Mexico City. Centro de Estudios Nucleares; Guanajuato Univ. (Mexico); 79 p; 1984; p. 37; 5. Symposium on nuclear chemistry, radiochemistry and radiation chemistry; Guanajuato (Mexico); 4-7 Dec 1984; Published in summary form only.
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[en] The most common basic process of air detritiation, which employs oxidation of tritiated gases in a catalytic recombiner and subsequent collection of HTO on molecular sieve dryers, can also be used for a large-scale detritiation system for the next-step deuterium-tritium fusion device. Performance, economy, and reliability can be improved by modifying the design of basic elements, i.e., the recombiners and molecular sieve dryers, and by rearranging them in a system permitting multiple process path choices for optimum performance depending on demand. These improvements should result in a system that is (a) free of secondary tritium release by permeation; (b) economical, with <1 kW power required in a ready-to-operate open-quotes hot standbyclose quotes condition; (c) capable of reducing inlet humidity of the order of 10 000 ppm (volume) to 0.01 ppm at the outlet by using two adsorber stages in series; and (d) capable of providing the best starting condition for water processing: little or no dilution by H2O from isotopic swamping due to the use of two adsorber stages. The system detritiation factor is defined and discussed, and the overriding importance of high water retention efficiency is demonstrated. 4 refs., 5 figs
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[en] An attempt is made to estimate the lithium reserve (the economically recoverable lithium) for the tritium breeding in D-T fusion reactors and other uses. Similar development patterns for fusion energy and fission energy are assumed to estimate the future lithium requirements. These requirements are grouped into three categories; the commercial uses, the lithium batteries for electric cars, and the fusion reactor uses. 5 refs
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2. Miami international conference on alternative energy sources; Miami Beach, FL (USA); 10 - 13 Dec 1979; CONF-791204--
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Alternative Energy Sources; v. 6 p. 2535-2538
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[en] Published in summary form only
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Sao Paulo Univ., SP (Brazil); 277 p; 1988; p. 238; 4. International Symposium on Radiation Physics; Sao Paulo, SP (Brazil); 3-7 Oct 1988
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AbstractAbstract
[en] A method is proposed which should allow to pump the exhaust (including He) from a fusion reactor. The scrape-off-layer plasma which is neutralized at the limiter or divertor plate streams into a pumping discharge where it is ionized and is then guided along magnetic field lines into a separate pumping chamber where it is again neutralized. This procedure allows one to create an intermediate pressure step after which ordinary pumps can be used which are no longer exposed to direct neutron radiation. (orig.)
[de]
Es wird eine Methode vorgeschlagen, mit der ein Abpumpen des Abgases (einschl. He) aus einem Fusionsreaktor moeglich sein sollte. Das an der Begrenzer- oder Ableitplatte neutralisierte Plasma der abgezogenen Schicht stroemt in einen Pumpenablauf, wo es ionisiert und laengs der Magnetfeldlinien in eine getrennte Pumpenkammer gefuehrt wird, um dort wieder neutralisiert zu werden. Bei diesem Verfahren kann eine zusaetzliche Druckstufe eingefuehrt werden, nach der gewoehnliche Pumpen, die nicht mehr einer Neutronenstrahlung ausgesetzt sind, benutzt werden koennen. (orig.)Primary Subject
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Dec 1980; 14 p
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