Overview of JET results

Paméla, J.; Ongena, J.; Contributors, Jet

doi:10.1088/0029-5515/51/9/094008

Cited by 41 publications

(50 citation statements)

References 66 publications

(78 reference statements)

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“…(67) yields about 2 MN, which gives a correct order of magnitude of the sideways force measured in JET. 2,3,5,[9][10][11]13,56,57 The estimates are obtained assuming large-amplitude m ¼ n ¼ 1 magnetic perturbation, but actually without attributing it to the plasma. For the ideal plasma, Eqs.…”

Section: Estimates Of the Sideways Forcementioning

confidence: 99%

Analytical model of wall forces produced by kink perturbations in tokamaks

Mironov

Pustovitov

2015

Phys. Plasmas

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Analytical model of the electromagnetic forces produced by kink modes on the tokamak wall [H. R. Strauss et al., Phys. Plasmas 17, 082505 (2010)] is revisited. One of the main conclusions of the mentioned paper is that the largest force occurs at cs w % 1, where c is the kink growth rate and s w is the wall penetration time. In the present study, a similar approach is developed under less restrictive assumptions on the plasma and dynamics of perturbation, and a different result is obtained: the force increases with c and must be maximal at cs w ! 1. Additionally, the dependence of its amplitude on the plasma parameters is clarified. All distinctions and their reasons are explained in detail. The analysis is performed in the cylindrical model incorporating a resistive wall treated without traditional thin-wall constraints and covering therefore a full range in cs w . It is applicable to either locked or rotating modes. Estimates of the sideways force are presented and compared with earlier forecasts. V C 2015 AIP Publishing LLC. [http://dx.

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Section: Estimates Of the Sideways Forcementioning

confidence: 99%

Analytical model of wall forces produced by kink perturbations in tokamaks

Mironov

Pustovitov

2015

Phys. Plasmas

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“…Specifically, we investigate a new FAST scenario at I p ¼ 10 MA, B T ¼ 8.5 T, with a q 95 % 2.3 that would correspond to I p % 20 MA in ITER. The possibility to safely work at q 95 < 3 (q 95 % 2.6) has been shown recently at JET, 7 although with a slight degradation of the energy confinement (H 98 % 0.9). The key point is to demonstrate in FAST, for such a low-q scenario, the possibility of using passive conducting structures and active coils to stabilize and control potentially dangerous ideal and resistive MHD modes.…”

Section: Introductionmentioning

confidence: 92%

“…2. Of course, an accurate tailoring of the current rise 7 and of the plasma heating will be necessary to drive the current profile towards the most convenient (stable) situation. An internal q ¼ 1 surface may eventually appear; nevertheless, in the present study, we have considered only equilibria without a q ¼ 1 surface, in order to allow an easier analysis of external kink and tearing instabilities.…”

Section: A Equilibrium Configurationsmentioning

confidence: 99%

Magnetohydrodynamic modes analysis and control of Fusion Advanced Studies Torus high-current scenarios

Villone¹,

Calabrò²,

Marchiori³

et al. 2014

Physics of Plasmas

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One of the main FAST (Fusion Advanced Studies Torus) goals is to have a flexible experiment capable to test tools and scenarios for safe and reliable tokamak operation, in order to support ITER and help the final DEMO design. In particular, in this paper, we focus on operation close to a possible border of stability related to low-q operation. To this purpose, a new FAST scenario has then been designed at I-p = 10 MA, B-T = 8.5 T, q(95) approximate to 2.3. Transport simulations, carried out by using the code JETTO and the first principle transport model GLF23, indicate that, under these conditions, FAST could achieve an equivalent Q approximate to 3.5. FAST will be equipped with a set of internal active coils for feedback control, which will produce magnetic perturbation with toroidal number n = 1 or n = 2. Magnetohydrodynamic (MHD) mode analysis and feedback control simulations performed with the codes MARS, MARS-F, CarMa (both assuming the presence of a perfect conductive wall and using the exact 3D resistive wall structure) show the possibility of the FAST conductive structures to stabilize n = 1 ideal modes. This leaves therefore room for active mitigation of the resistive mode (down to a characteristic time of 1 ms) for safety purposes, i.e., to avoid dangerous MHD-driven plasma disruption, when working close to the machine limits and magnetic and kinetic energy density not far from reactor values. (C) 2014 AIP Publishing LLC

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“…It is well known that high-temperature plasma in tokamaks is never completely stable [1]. One can observe different instabilities, e.g.…”

Section: Introductionmentioning

confidence: 99%

“…The performed computer calculations showed that the confi nement of alphas for further plasma heating can be realized under specifi c conditions in large tokamaks only [1]. To estimate effi ciency of fast ion confi nement, the simulations require analysis of multi-dimensional distribution functions for multi-species plasma and they take many computer hours.…”

Section: Introductionmentioning

confidence: 99%

Selected methods of electron-and ion-diagnostics in tokamak scrape-off-layer

Sadowski

2015

Nukleonika

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Abstract. This invited paper considers reasons why exact measurements of fast electron and ion losses in tokamaks, and particularly i n a scrape-off-layer and near a divertor region, are necessary in order to master nuclear fusion energy production. Attention is also paid to direct measurements of escaping fusion products from D-D and D-T reactions, and in particular of fast alphas which might be used for plasma heating. The second part describes the generation of so-called runaway and ripple-born electrons which might induce high energy losses and cause severe damages of internal walls in fusion facilities. Advantages and disadvantages of different diagnostic methods applied for studies of such fast electrons are discussed. Particular attention is paid to development of a direct measuring technique based on the Cherenkov effect which might be induced by fast electrons in appropriate radiators. There are presented various versions of Cherenkov-type probes which have been developed by the NCBJ team and applied in different tokamak experiments. The third part is devoted to direct measurements of fast ions (including those produced by the nuclear fusion reactions) which can escape from a high-temperature plasma region. Investigation of fast fusion-produced protons from tokamak discharges is reported. New ion probes, which were developed by the NCBJ team, are also presented. For the fi rst time there is given a detailed description of an ion pinhole camera, which enables irradiation of several nuclear track detectors during a single tokamak discharge, and a miniature Thomson-type mass-spectrometer, which can be used for ion measurements at plasma borders.

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Overview of JET results

Cited by 41 publications

References 66 publications

Analytical model of wall forces produced by kink perturbations in tokamaks

Analytical model of wall forces produced by kink perturbations in tokamaks

Magnetohydrodynamic modes analysis and control of Fusion Advanced Studies Torus high-current scenarios

Selected methods of electron-and ion-diagnostics in tokamak scrape-off-layer

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