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Hobirk, J.; Bernert, M.; Pütterich, T.; Buratti, P.; Pucella, G.; Challis, C.D.; Mailloux, J.; Coffey, I.; Drewelow, P.; Joffrin, E.; Nunes, I.; De Vries, P.C., E-mail: joerg.hobirk@ipp.mpg.de
JET Contributors2018
JET Contributors2018
AbstractAbstract
[en] This paper analyses the final phase of hybrid scenario discharges at JET, the reduction of auxiliary heating towards finally the Ohmic phase. The here considered Ohmic phase is mostly still in the current flattop but may also be in the current ramp down. For this purpose a database is created of 54 parameters in 7 phases distributed in time of the discharge. It is found that the occurrence of a locked mode is in most cases preceded by a radiation peaking after the main heating phase either in a low power phase and/or in the Ohmic phase. To gain insight on the importance of different parameters in this process a correlation analysis to the radiation peaking in the Ohmic phase is done. The first finding is that the further away in time the analysed phases are the less the correlation is. This means in the end that a good termination scenario might also be able to terminate unhealthy plasmas safely. The second finding is that remaining impurities in the plasma after reducing the heating power in the termination phase are the most important reason for generating a locked mode which can lead to a disruption. (paper)
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Available from http://dx.doi.org/10.1088/1741-4326/aac526; Country of input: International Atomic Energy Agency (IAEA)
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Cairns, R.; Lashmore-Davies, C.
EURATOM/UKAEA Fusion Association, Abingdon (United Kingdom)2000
EURATOM/UKAEA Fusion Association, Abingdon (United Kingdom)2000
AbstractAbstract
No abstract available
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Feb 2000; 29 p; Available from British Library Document Supply Centre- DSC:9091.900(UKAEA-FUS-423)
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AbstractAbstract
[en] In order to establish the physics basis for the sustainment of the high integrated performance required in the next-step experimental reactor, JT-60U has been optimizing the discharge control scenarios of high confinement plasmas and extending the operation regimes by utilizing a variety of heating and current drive systems, including the new Electron Cyclotron Heating/Electron Cyclotron Current Drive (ECH/ECCD) system, and the W-shaped pumped divertor. For the integration, current and pressure profile controls are essential and high triangularity δ is beneficial. The range of plasma current with high values of H-factor, βN and bootstrap fraction was extended to 1.5 MA with nearly full non-inductive current drive by Negative-ion-based Neutral Beam (N-NB) injection into the high-βp H-mode with Edge Localized Modes (ELMy H-mode). High current drive efficiency of 1.3x1019 A W-1 m-2 was demonstrated for N-NB. High triangularity (0.4-0.5) operation extended the long pulse (∼3 s) high βN (2.5-2.7) region to low-q95 (∼3). For the reversed shear (RS) mode, feedback control of neutron production rate and stored energy enabled reproducible achievement of the DT equivalent fusion gain QeqDT>1 and sustainment of QeqDT∼0.4-0.5 for ∼1 s. Using the RS mode and the high δ high-βp ELMy H-mode, the high confinement region has been extended to higher Te/Ti and also to higher density. Electron heating by Lower Hybrid Range of Frequency (LHRF) and N-NB extended the high confinement region to Te/Ti>1. Argon gas puffing improved confinement in the high density regime. With the W-shaped pumped divertor, the threshold heating power for the L-H transition was reduced by 30% as compared with the open divertor. Using the pumped divertor, a multiple parameter feedback control including both core and divertor plasma parameters was demonstrated. (author)
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26. European Physical Society conference on plasma physics and controlled fusion; Maastricht (Netherlands); 14-18 Jun 1999
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Plasma Physics and Controlled Fusion (Online); ISSN 1361-6587;
; v. 41(12B); p. B77-B92

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AbstractAbstract
[en] We propose a new kind of transit-time interaction in which the reversal (or any localized transition) in the phase velocity of a wave within a wavelength of an antenna results in a high rate of work done by the wave (1/2 Re(j·E*)) near the antenna for conditions where the wave phase velocity is greater than a few times the thermal speed. This enhanced rate of work near the antenna can significantly exceed the far-field value due to Landau damping. For the conditions of typical low-field (< 0.01 T) and low-density (<1018m-3) helicon wave-driven plasma sources, where the phase velocity parallel to the magnetic field can be a few times the thermal speed of electrons, it has been demonstrated that this spatial transient overshoot in the rate of work done by the wave is the dominant kinetic energy coupling process to electrons). In this paper it is demonstrated that, within a half wavelength of the antenna, it is the high-energy electrons that gain energy from both the wave and low velocity electrons as a result of this process. An important practical consequence is that the ionization rate of neutral gas can be significantly enhanced above the Maxwellian rate. The phenomenon is not restricted to helicon sources. This process may also explain the production of high-energy electrons in the near fields of antennas used in fusion plasma heating by radiofrequency waves. (author)
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Journal Article
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Plasma Physics and Controlled Fusion (Online); ISSN 1361-6587;
; v. 40(6); p. 987-1000

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De Vries, P.C.; Johnson, M.F.; Alper, B.; Hender, T.C.; Riccardo, V.; Koslowski, R., E-mail: Peter.de.Vries@jet.efda.org
JET-EFDA Contributors
23. IAEA Fusion Energy Conference. Book of Abstracts2010
JET-EFDA Contributors
23. IAEA Fusion Energy Conference. Book of Abstracts2010
AbstractAbstract
[en] Full text: Disruptions have been able to cause considerable damage in larger devices like JET, hence prevention or mitigation is essential. In order to obtain a more precise insight in the occurrence of disruptions in large Tokamaks, a detailed survey has been carried out at JET. Firstly, the average fraction of plasmas that disrupt, or disruption rate, and the so-called disruptivity, i.e. the likelihood of a disruption depending on operational parameters, have been determined. Secondly a survey into the causes of all disruptions at JET was devised. The aim of these studies is to find out what factors determine the occurrence of disruptions and what sets the lower limit. Moreover, the knowledge of the disruption causes can be used to devise better strategies to prevent and mitigate disruptions at JET and possibly in ITER. The average disruption rates for various periods during 25 years of JET operations was found to decrease steadily and recent campaigns show an averaged rate of less than 4% while from 1991 to 1995 this was often higher than 20 - 30%. Higher disruption rates were found during exploratory campaigns while disruptions occurred much less frequently when disruption avoidance was essential, such during D-T operations. This suggests that occurrence of disruptions may partly be connected to less careful operations and human errors and the downward trend could be interpreted as a learning curve of Tokamak operations. To shed more light on this a detailed study into the causes of all disruptions over the period from 2000 to 2007 was conducted. This allowed the visualization of the complex chain-of-events that could lead to disruptions. As expected all disruptions at JET were eventually pushed close an operational limit resulting in the on-set of physics instabilities. But it was also found that the chain-of-events were often triggered (root cause) by rather technical problems such as the failure of sub-systems such as auxiliary heating. Human error was the second highest root cause of disruptions at JET. This paper will discuss the complete set of root causes and disruption classes that were found at JET. This study provided new insights in the processes that cause disruptions at JET and provided useful suggestions on how to prevent them. This work was partly funded by EURATOM, FOM and CCFE Contract of Association and carried out under EFDA. (author)
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International Atomic Energy Agency, Vienna (Austria); 637 p; Oct 2010; p. 168; FEC 2010: 23. IAEA Fusion Energy Conference; Daejeon (Korea, Republic of); 11-16 Oct 2010; EXS--P2-04; Also available on-line: http://www-pub.iaea.org/MTCD/Meetings/PDFplus/2010/cn180/cn180_BookOfAbstracts.pdf
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AbstractAbstract
[en] The JET gas baking plant allows the vacuum vessel to be heated for conditioning and plasma operations. The vessel was maintained at 320 deg. C for the JET DT experiments (DTE 1). The design of the plant is outlined with particular reference to the features to provide compatibility with tritium operations. The experience of baking gas activation and tritium permeation into the plant are given, Developments to reduce the tritium permeation out of the vessel are considered. (authors)
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Beaumont, B.; Libeyre, P.; Gentile, B. de; Tonon, G. (Association Euratom-CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee); (v.1-2) 1744 p; 1998; p. 1001-1004; 20. symposium on fusion technology; Marseille (France); 7-11 Sep 1998; 6 refs.
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Hartmann, D.A.; Cattanei, G.
W7-AS Team; ICRF Group
17. IAEA fusion energy conference. Extended synopses1998
W7-AS Team; ICRF Group
17. IAEA fusion energy conference. Extended synopses1998
AbstractAbstract
No abstract available
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Source
International Atomic Energy Agency, Vienna (Austria); 379 p; 1998; p. 73; 17. IAEA fusion energy conference; Vienna (Austria); 19-24 Oct 1998; CD--1/5; 1 ref
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Murmann, H.; Wagner, F.; Becker, G.; Bosch, H.S.; Brocken, H.; Eberhagen, A.; Fussmann, G.; Gehre, O.; Gernhardt, J.; Gierke, G. v.; Glock, E.; Gruber, O.; Haas, G.; Hofmann, J.; Janeschitz, G.; Karger, F.; Klueber, O.; Kornherr, M.; Lackner, K.; Lenoci, M.; Lisitano, G.; Mast, F.; Mayer, H.M.; McCormick, K.; Meisel, D.; Mertens, V.; Niedermeyer, H.; Poschenrieder, W.; Rapp, H.; Roehr, H.; Roth, J.; Schneider, F.; Setzensack, C.; Siller, G.; Soeldner, F.X.; Steuer, K.H.; Zasche, D.; Izvozchikov, A.; Ryter, F.
ASDEX papers at the 13th European conference on controlled fusion and plasma physics1986
ASDEX papers at the 13th European conference on controlled fusion and plasma physics1986
AbstractAbstract
[en] A crucial and still unsolved problem in tokamak physics is the understanding of anomalous heat transport across the magnetic field via heat conduction of the electrons. All efforts to establish a universal expression for the diffusivity Χe as a function of local plasma parameters which is valid also for auxiliary heating have failed so far. The problem has become even greater since it became evident that plasma confinement deteriorates during additional heating in a parameter range that is still very close to ohmic heating conditions. (orig./GG)
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Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.); 149 p; May 1986; p. 41-44; 13. European conference on controlled fusion and plasma heating; Schliersee (Germany, F.R.); 14-18 Apr 1986
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Sakamoto, Keishi; Kasugai, Atsushi; Tsuneoka, Masaki; Takahashi, Koji; Ikeda, Yukiharu; Imai, Tsuyoshi; Kariya, Tsuyoshi; Mitsunaka, Yoshika
17. IAEA fusion energy conference. Extended synopses1998
17. IAEA fusion energy conference. Extended synopses1998
AbstractAbstract
No abstract available
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Source
International Atomic Energy Agency, Vienna (Austria); 379 p; 1998; p. 283; 17. IAEA fusion energy conference; Vienna (Austria); 19-24 Oct 1998; FTP--23(R)-FT1/4(R); 2 refs, 2 figs, 1 tab
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AbstractAbstract
[en] The diacrode concept has been already successfully developed and tested by Thomson Tubes Electroniques. Demonstration is done that ITER project requirements cannot be met with a single tetrode power amplifier but with one new diacrode, the design of the RF circuit around which is hereafter proposed. (author)
Primary Subject
Source
Beaumont, B.; Libeyre, P.; Gentile, B. de; Tonon, G. (Association Euratom-CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Recherches sur la Fusion Controlee); (v.1-2) 1744 p; 1998; p. 323-326; 20. symposium on fusion technology; Marseille (France); 7-11 Sep 1998
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