Conveners
MCF
- G. Granucci (ISTP Milano - CNR)
MCF
- K. Crombé (Department of Applied Physics| Ghent University| Belgium)
MCF
- R. Coelho (Instituto Superior Tecnico)
MCF
- E. Wolfrum (Max Planck Inst. f. Plasmaphysik)
MCF
- H.-S. Bosch (EPS2019)
MCF
- C. Maggi (CCFE)
MCF
- R. Ding
MCF
- G. Pautasso
MCF
- R. Panek (Institute of Plasma Physics ASCR| Prague)
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J. Stober (EPS 2019)7/8/19, 4:30 PMMCF
See the full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/I1.101.pdfThe ECRH system of ASDEX Upgrade has been upgraded over the last 15 years from a 2 MW, 2 s, 140 GHz system to an 8 MW, 10 s, dual frequency system (105/140 GHz). The power exceeds the L/H power threshold at least by a factor of two even for high densities and roughly equals the installed ICRF power. The power of both...
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G. Giruzzi (EPS 2019)7/8/19, 5:00 PMMCF
See the full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/I1.102.pdfJT-60SA is a large fully superconducting new tokamak device being built jointly by Europe and Japan, and due to start operation in 2020 [1]. In this prospect, a broad set of preparation activities [2] has been carried out for years, involving the elaboration of the JT-60SA Research Plan [3], and is now focusing on the...
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M. Nocente (EPS 2019)7/8/19, 5:30 PMMCF
See the full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/I1.103.pdfEnergetic particles in the MeV range are ubiquitous in fusion devices [1]. On one hand, they can be suprathermal ions born from the fusion reactions or accelerated by ion cyclotron resonance heating. On the other hand, they can be runaway electrons (REs) that are spontaneously generated, for example, during a...
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Y. Todo (EPS 2019)7/8/19, 6:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I1.104.pdf
Magnetohydrodynamics (MHD) is a theoretical framework that explains well the macroscopic plasma behaviours. However, MHD is an unfinished framework for magnetically confined plasmas, because the MHD pressure equation assumes sufficiently high collision frequency which is not valid for the high-temperature plasmas. One...
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H. Reimerdes (EPS 2019)7/9/19, 10:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I2.101.pdf
The European roadmap for fusion energy has identified plasma exhaust as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the baseline scenario with a single null divertor (SND) and a high radiation fraction adopted for ITER will not extrapolate to a DEMO reactor, the...
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T.M. Wauters (EPS 2019)7/9/19, 10:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I2.102.pdf
This contribution reviews the currently applied wall conditioning methods in fusion devices with special emphasis on wall conditioning in the presence of a permanent magnetic field by applying RF discharges at the ion- and electron cyclotron range of frequencies (ICRF resp. ECRF). The review is built upon the results of...
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A. Drenik (EPS 2019)7/9/19, 11:10 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I2.103.pdf
To prevent damage to the divertor target plates, impurity seeding will be unavoidable in ITER. Among the tested impurities, nitrogen (N) is the most likely candidate impurity. Besides promoting the radiation in the plasma edge, nitrogen seeding also provides improved confinement in existing tokamaks. The drawback of...
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T.A. Lunt (EPS 2019)7/9/19, 11:10 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.101.pdf
Power exhaust is expected to become a problem in a future fusion reactor based on the Tokamak design in conventional single-null (SN) configuration. As a potential solution, alternative divertor geometries are currently discussed and investigated by many laboratories in the world [1]. In order to study a series of...
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P. Martin (EPS 2019)7/9/19, 11:25 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.102.pdf
Appropriate disposal of the non-neutronic energy and particle exhaust in a reactor is universally recognized as one of the high priority challenges for the exploitation of fusion as an energy source. The new Divertor Tokamak Test (DTT) facility, which will be built in Italy, is a tool to address that challenge in...
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F. Riva (EPS 2019)7/9/19, 11:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.103.pdf
In the present work, global, three-dimensional edge plasma turbulence simulations of a MAST L-mode attached plasma discharge are presented. Our study is based on the driftreduced Braginskii equations, solved with the STORM module of BOUT++ for realistic MAST parameters in disconnected lower double null configuration....
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A. Kirschner (EPS 2019)7/9/19, 11:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.107.pdf
Tungsten (W) is a candidate for plasma-facing components in future fusion reactors like DEMO and already used in fusion experiments like JET-ILW and ITER, which is currently under construction. It is foreseen for wall areas of highest particle and power loads as it has high melting point and low physical sputter yield....
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N. Ohana (EPS 2019)7/9/19, 11:55 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.104.pdf
In order to get a better understanding of the linear and nonlinear plasma interaction of microinstabilities and associated turbulence with different specific modes, an antenna is implemented in the global gyrokinetic code ORB5. It consists in applying external chargeand current-density perturbations or, alternatively,...
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C.D. Challis (EPS 2019)7/9/19, 11:55 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.108.pdf
The initial current ramp phase of JET hybrid plasmas is used to optimise the q-profile to allow access to high beta and avoid MHD instabilities. Mixed protium-deuterium experiments have shown that the q-profile evolution during this phase varies systematically with average main ion isotope mass (Meff), as seen in Fig.1,...
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M. Griener (EPS 2019)7/9/19, 12:10 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.105.pdf
In magnetic confinement fusion, transport processes in the plasma edge region determine the power load onto the first wall materials which has to be minimized on the way towards a fusion power plant. While a main fraction of the power is transported parallel to the magnetic field lines to the divertor, a significant...
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A.V. Dudkovskaia (EPS 2019)7/9/19, 12:10 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.109.pdf
Understanding the physics of the NTM onset and its suppression is a key problem in achieving controlled fusion. This requires better knowledge of the NTM threshold mechanism.
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We solve the drift kinetic equation for the ion/electron response to the NTM magnetic perturbation, gi,e, assuming small magnetic island width,... -
A.A. Stepanenko (EPS 2019)7/9/19, 12:25 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.106.pdf
Observations of divertor plasma turbulence in a series of experiments at the DIII-D tokamak has recently demonstrated the onset of parallel current and magnetic field fluctuations [1] with temporal parameters similar to those reported for the fluctuations of divertor plasma radiation intensity at the ASDEX Upgrade...
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L. Gil (EPS 2019)7/9/19, 12:25 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.110.pdf
The H-mode is the preferable operation regime for a fusion reactor due to its superior confinement properties, but it comes with a major drawback: edge-localized modes (ELMs). These instabilities lead to unacceptably high heat loads on the divertor when extrapolated to large-scale machines [1]. The ELM-free phases...
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M. van Berkel (EPS 2019)7/9/19, 4:30 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I2.104.pdf
In perturbative experiments, the power deposition profile is a crucial ingredient in the analysis of the (turbulent) transport [1, 2]. Typically, the deposition profile is calculated with a forward model and used for the computation of the transport [3, 4, 5]. We will show that allowing for uncertainties in the...
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R. McDermott (EPS 2019)7/9/19, 5:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I2.105.pdf
Impurities are unavoidable in fusion plasmas and potentially highly problematic as they result in fuel dilution and radiative energy losses. Accurate predictions of fusion plasma performance, therefore, require a validated theoretical description of impurity transport, which in turn requires high accuracy measurements...
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K. Tanaka (EPS 2019)7/9/19, 5:30 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I2.106.pdf
In LHD, hydrogen and deuterium isotope experiments were extensively carried out from the 2017 experimental campaign. In ECRH plasma, positive isotope effects in global energy confinement time taoE ECH proportional to A^(0.22±0.01) ne bar ^(0.60±0.01) Pabs^(-0.51±0.01) and negative isotope effects in global particle...
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U. Plank (EPS 2019)7/9/19, 6:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.111.pdf
Understanding the dependence of the H-mode power threshold, PLH, on the main ion composition is critical for the pre-nuclear operational phase of ITER, which will be perfomed in H and He plasmas. For pure H plasmas it is well known that PLH(H) = 2PLH(D), while in the case of pure He plasmas the results vary between...
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E. Caschera (EPS 2019)7/9/19, 6:15 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O2.112.pdf
Turbulent transport and its impact on ITER performance is investigated with the global flux-driven gyrokinetic code GYSELA. In that framework, a heat source, balanced by turbulent cross-field transport, determines the temperature profile. It is expected that the heat sink at the boundary and turbulence in the edge may...
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O. Schmitz (EPS 2019)7/10/19, 10:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I3.101.pdf
The island divertor concept is an innovative and promising idea to handle heat and particle exhaust in stellarators. At the recently started stellarator Wendelstein 7-X, this divertor concept plays a central role in the device mission to demonstrate reactor relevant plasma confinement for steady-state time scales of up...
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J.A. Alonso (EPS 2019)7/10/19, 11:10 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I3.102.pdf
Two of the highest priorities in stellarator research are to verify the effects of orbit driftoptimization on the energy core confinement and to learn to prevent the accumulation of impurities in high-density plasmas. The basic framework for understanding energy and particle transport in these devices is neoclassical...
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N.A. Pablant (EPS 2019)7/10/19, 11:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O3.101.pdf
The role of the radial electric field in high performance ion-root plasmas on Wendelstein 7-X (W7-X) is examined and compared with neoclassical predictions. In stellarator plasmas the neoclassical radial electric field (Er) is not intrinsically ambipolar, and is instead strongly tied to the plasma profiles. The...
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T. Oishi (EPS 2019)7/10/19, 11:55 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O3.102.pdf
The ergodic layer located at the plasma edge of Large Helical Device (LHD) consists of stochastic magnetic fields with three-dimensional structure intrinsically formed by helical coils. Reduction of impurity penetration into confinement region due to existence of the ergodic layer, so called "impurity screening", has...
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K. Nagasaki (EPS 2019)7/10/19, 12:10 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O3.103.pdf
Energetic alpha particles generated by D-T fusion reaction and beam ions for plasma heating interact resonantly with shear Alfvén waves through damping process when their velocity is comparable with Alfvén velocity, resulting in excitation of energetic particle (EP)-driven MHD instabilities. Several types of EP-driven...
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P.T. Lang (EPS 2019)7/10/19, 12:25 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O3.104.pdf
Operation in a future fusion reactor will aim to establish a high plasma core density n0 in order to harvest a maximum output power. Hence, for example the near term EU-DEMO1 concept foresees operation at n0 values at or even beyond 1.2 the Greenwald density nGw. Like for most envisaged reactor scenarios this approach...
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S. Bozhenkov (EPS 2019)7/10/19, 12:40 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O3.105.pdf
High-density operation is an attractive target for a fusion reactor, as it raises the fusion power output. Stellarators are especially suitable for such a regime, because they are not restricted by the disruptive density limit and because their energy confinement is roughly proportional to the square root of the...
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E. Viezzer (EPS 2019)7/11/19, 10:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I4.101.pdf
Recent advances in the diagnostic capabilities at ASDEX Upgrade (AUG) allow us to measure the edge profiles on a sub-ms timescale and with a spatial resolution of less than 5 mm. This makes it ideal to study the profile recovery during fast transient events. Here, we present the dynamic behaviour of the energy, particle...
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D. Hatch (EPS 2019)7/11/19, 11:10 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I4.102.pdf
An ITER-like wall (ILW), composed of a tungsten divertor and beryllium chamber, was installed on JET in order to study material erosion and tritium retention in preparation for ITER. The ILW has successfully demonstrated long-term tritium retention but has had an unexpected impact on confinement via its effect on the...
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A. Ashourvan (EPS 2019)7/11/19, 11:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.101.pdf
We observe the formation of a high-pressure staircase pedestal (~16-20 kPa) in high beta p plasmas (beta p>1.5) in the DIII-D tokamak when large amplitude ELMs are suppressed using resonant magnetic perturbations (RMP). The pedestal cyclically transitions from a one-step structure to a wider two-step staircase...
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L. Horvath (EPS 2019)7/11/19, 11:55 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.102.pdf
A strong, favourable isotope dependence of the energy confinement (tao E,th ~ A^0.4) has been found in Hydrogen (H) and Deuterium (D) JET-ILW type I ELMy H-modes, originating at the pedestal [1]. Also, the plasma density is systematically lower in H than in D plasmas [1]. This contribution examines the isotopic...
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A. Diallo (EPS 2019)7/11/19, 12:10 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.103.pdf
We report on recent investigations in DIII-D of three-wave interactions between pedestal modes during quasi-stationary inter-ELM phases leading up to the type I ELM onset. Prior to eruptive events such as ELMs, these pedestal modes, also called quasi-coherent fluctuations, are observed in the edge of fusion devices[1]....
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G.F. Harrer (EPS 2019)7/11/19, 12:25 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.104.pdf
In future fusion devices the collisionality Nue proportional to ne/Te^2 at the pedestal top will be very low, i.e. nue,pedtop ∼0.06 [1], due to the expected high temperature. On the other hand at the very edge it should be high, nu*e,sep ∼12, because a high separatrix density is necessary for efficient power exhaust....
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S. Wiesen (EPS 2019)7/11/19, 4:30 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I4.103.pdf
Power exhaust in future electricity producing fusion device like DEMO features difficulties which, compared to ITER, are harder to tackle in terms of operational control requiring an improved physics understanding. For a given power loss density Ploss/R the plasma facing components need to withstand a maximum heat flux...
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G. Papp (EPS 2019)7/11/19, 4:30 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I4.105.pdf
Developing a disruption & runaway electron (RE) mitigation strategy that robustly scales to ITER and beyond is a major challenge. The dynamics is governed by a complex interplay of effects such as the atomic physics and penetration of the high-Z material injected for mitigation, quench dynamics (MHD), kinetic physics,...
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J. Harrison (EPS 2019)7/11/19, 5:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I4.104.pdf
The operation of future high-power density fusion reactors such as ITER and DEMO requires avoiding damaging plasma-facing surfaces and good core confinement. The former requirement necessitates operating in the detached divertor regime, and the latter is met by operating in the high confinement (H-) mode. Recent...
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D. Shiraki (EPS 2019)7/11/19, 5:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I4.106.pdf
Recent advances in shattered pellet injection (SPI) in the DIII-D tokamak have led to improved understanding of several critical issues for the ITER Disruption Mitigation System. Infrared thermography shows elevated thermal quench heat loads indicative of radiation asymmetries peaked near the injection source. However...
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A. Leonard (EPS 2019)7/11/19, 5:30 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.105.pdf
A comprehensive diagnostic set compared against 2D modeling has provided new insight into energy transport and dissipation processes in detached plasmas and their scaling to future devices. Experiments and modeling reveal a detached divertor plasma dominated by plasma convection from the X-point towards the target....
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L. Piron (EPS 2019)7/11/19, 5:30 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.109.pdf
The presence of Error Fields (EFs) in magnetic fusion devices can affect energy confinement and plasma stability by braking plasma rotation, by inducing fast particle losses and being amplified when exploring high- regimes. The resulting EF Locked Modes (LMs) can be stabilized by NBI injection through the rotation...
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T.H. Eich (EPS 2019)7/11/19, 5:45 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.106.pdf
Operation of tokamaks with H-Mode characteristics and at high densities is generally foreseen for future high-power fusion systems, including ITER. The ease of access to divertor detachment via impurity seeding scales to first order proportional to (n_sep/n_GW)^2 lambda_q/rho_s,pol [1] with lambda_q being the power...
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F. Villone (EPS 2019)7/11/19, 5:45 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.110.pdf
Disruptions are one of the fundamental issues to be tackled in future tokamaks [1], due to significant eddy and halo currents in the conducting structures producing substantial electromagnetic forces and torques thanks to the interaction with the magnetic field. It is hence fundamental to have reliable modelling tools...
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X. Gong (EPS 2019)7/11/19, 6:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.107.pdf
A 100 sec long-pulse steady-state H-mode plasma with good energy confinement (H98(y,2) ~ 1.1) has been successfully achieved on EAST using RF heating and current drive. Recent EAST experiments with improved hardware capabilities have demonstrated steady-state fully non-inductive scenarios with extension of fusion...
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F.J. Artola (EPS 2019)7/11/19, 6:00 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.111.pdf
The growing need for a fundamental understanding of complex MHD phenomena in diverted tokamaks requires the development of more sophisticated and highly demanding codes. The numerical MHD code JOREK-STARWALL is adapted and applied to the simulation of free-boundary instabilities. The investigation of this type of...
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M. Faitsch (EPS 2019)7/11/19, 6:15 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.108.pdf
In recent years the focus of tokamak fusion research onto power exhaust increased showing that first wall power load is one of the major challenges in realizing a power plant. Unmitigated divertor power loads in next step fusion devices like ITER are projected to exceed material limits making significant impurity...
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Y. Park (EPS 2019)7/11/19, 6:15 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O4.112.pdf
Long-pulse plasma operation at high normalized beta up to 4 (exceeding the n = 1 ideal MHD no-wall stability limit) in KSTAR is presently limited by tearing instabilities rather than resistive wall modes that are computed to be stabilized by kinetic MHD effects. H-mode plasma operation during the 2018 KSTAR device...
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J. Huang (EPS 2019)7/12/19, 10:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I5.101.pdf
Significant progress has been achieved along the China's roadmap towards tokamak based fusion energy production. The three-pronged approach towards the Chinese Fusion Engineering Test Reactor (CFETR) will be reported.
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Recently, EAST achieved the first demonstration of 100s time scale steady-state H-mode operation with... -
S.A. Henneberg (EPS 2019)7/12/19, 11:10 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/I5.102.pdf
Lausanne, Switzerland An extensive study of quasi-axisymmetric equilibria has been conducted, from which a highly promising magnetic field design has been found by exploiting ROSE (Rose Optimizes Stellarator Equilibria) [1] - an optimization code for 3D magnetic plasma equilibria. The results of this design study and...
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C. Bourdelle (EPS 2019)7/12/19, 11:40 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O5.101.pdf
WEST is a full tungsten (W) superconducting tokamak with a major radius of 2.5 m, an aspect ratio of 5 and a nominal magnetic field of 3.7T. WEST programme aims at power exhaust studies on the ITER-like actively cooled tungsten divertor and at bulk plasma performance in discharges reaching 1000s.
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So far up to 5.3 MW of... -
M. Mantsinen (EPS 2019)7/12/19, 11:55 AMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O5.102.pdf
Ion Cyclotron Resonance Frequency (ICRF) heating is one of the auxiliary heating methods which will be used in ITER. A detailed assessment of ICRF schemes available in the non-active phase of ITER operation was recently carried out [1]. As a result, the ICRF scenarios considered for ITER also include the so-called...
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D. Ricci (EPS 2019)7/12/19, 12:10 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O5.103.pdf
For an efficient and robust use of Electron Cyclotron (EC) to assist the start-up phase of the plasma in large tokamaks with superconductive coils, it is necessary to develop appropriate models capable of predicting from present experiments to future scenarios (as for ITER, JT60SA and DEMO). Experience gained on TCV and...
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M. Maslov (EPS 2019)7/12/19, 12:25 PMMCF
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/O5.104.pdf
Series of isotope control experiments in H/D mixtures on JET [1] have shown that NBI fuelling species has only a weak effect on the core isotope composition, which remains determined by the edge H/D ratio and therefore by the injected gas. The analysis of the core particle transport of the ion components revealed a fast...
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