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Fusion energy-production from a deuterium-tritium plasma in the jet tokamak
JET Team; REBUT, PH (reprint author), UKAEA,HARWELL LAB,HARWELL OX11 0RA,BERKS,ENGLAND.
1992
发表期刊Nuclear Fusion
卷号32期号:2页码:187-203
ISSN0029-5515
摘要Describes a series of experiments in the Joint European Torus (JET), culminating in the first tokamak discharges in deuterium-tritium fuelled mixture. The experiments were undertaken within limits imposed by restrictions on vessel activation and tritium usage. The objectives were: (i) to produce more than one megawatt of fusion power in a controlled way; (ii) to validate transport codes and provide a basis for accurately predicting the performance of deuterium-tritium plasmas from measurements made in deuterium plasmas; (iii) to determine tritium retention in the torus systems and to establish the effectiveness of discharge cleaning techniques for tritium removal; (iv) to demonstrate the technology related to tritium usage; and (v) to establish safe procedures for handling tritium in compliance with the regulatory requirements. A single-null X-point magnetic configuration, diverted onto the upper carbon target, with reversed toroidal magnetic field was chosen. Deuterium plasmas were heated by high power, long duration deuterium neutral beams from fourteen sources and fuelled also by up to two neutral beam sources injecting tritium. The results from three of these high performance hot ion H-mode discharges are described: a high performance pure deuterium discharge; a deuterium-tritium discharge with a 1% mixture of tritium fed to one neutral beam source; and a deuterium-tritium discharge with 100% tritium fed to two neutral beam sources. The TRANSP code was used to check the internal consistency of the measured data and to determine the origin of the measured neutron fluxes. In the best deuterium-tritium discharge, the tritium concentration was about 11% at the time of peak performance, when the total neutron emission rate was 6.0 × 1017 neutrons/s. The integrated total neutron yield over the high power phase, which lasted about 2 s, was 7.2 × 1017 neutrons, with an accuracy of ±7%. The actual fusion amplification factor, QDT was about 0.15
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收录类别SCI
语种英语
WOS记录号WOS:A1992HK41200001
WOS研究方向Physics
WOS类目Physics, Fluids & Plasmas ; Physics, Nuclear
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被引频次:107[WOS]   [WOS记录]     [WOS相关记录]
文献类型期刊论文
条目标识符http://dspace.imech.ac.cn/handle/311007/39488
专题力学所知识产出(1956-2008)
通讯作者REBUT, PH (reprint author), UKAEA,HARWELL LAB,HARWELL OX11 0RA,BERKS,ENGLAND.
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GB/T 7714
JET Team,REBUT, PH . Fusion energy-production from a deuterium-tritium plasma in the jet tokamak[J]. Nuclear Fusion,1992,32(2):187-203.
APA JET Team,&REBUT, PH .(1992).Fusion energy-production from a deuterium-tritium plasma in the jet tokamak.Nuclear Fusion,32(2),187-203.
MLA JET Team,et al."Fusion energy-production from a deuterium-tritium plasma in the jet tokamak".Nuclear Fusion 32.2(1992):187-203.
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