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D. Maurer (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1001.pdfThe Compact Toroidal Hybrid (CTH) is an l=2, m=5 torsatron/tokamak hybrid (R=0.75m, a~0.2m, and |B|<=0.5T) with the ability to vary the confining magnetic field configuration and generate rotational transform profiles that are tokamak-like with ohmically driven plasma current for disruption and MHD studies. The main goals...
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L. Pigatto (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1002.pdfThe forthcoming device JT-60SA, under construction in Naka (Japan), is particularly well equipped for studying Advanced Tokamak scenarios with high N and a non-negligible fraction of energetic particles from neutral bean injectors [1][2]. These plasmas are prone to exhibit kink-like ideal MHD instabilities; one or more...
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N. Isernia (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1003.pdfDisruptions are one of the major concerns in ITER and other future tokamaks [1]. In addition to heat, particle flux, and energetic electrons impacting the first wall, significant electromagnetic loads will arise, due to the interaction of eddy and halo currents in the conducting structures with the magnetic field....
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S. Wang (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1004.pdfActive control of the n = 1 (n is the toroidal mode number) resistive wall mode (RWM) is numerically studied, taking into account (i) recent design of the plasma equilibrium for the ITER 9 MA steady state scenario, and (ii) two important control aspects towards realistic modeling of the RWM feedback for ITER, namely the...
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T. Xu (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1005.pdfIn this work, we have constructed an ITER con guration, which is generated by currents owing within the plasma and currents owing in external coils. The plasma current density takes the form j_φ (r; z) = - ar - bR^2/r or other H-mode current pro le inside the plasma, and is zero in the surrounding vacuum. We use Green's...
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M. Dibon (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1006.pdfDisruption mitigation is one of the main research topics on the way to ITER and future Tokamak fusion power plants. Therefore, extensive studies have to be carried out on large Tokamaks to understand the physics and to develop the necessary technologies. JT-60SA, which will go into operation in 2020, will be a primary...
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C. Chen (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1007.pdfA new compact torus injection (KTX-CTI) system is being developed on Keda Torus eXperiment (KTX), which is a newly built medium size reversed field pinch device. The KTXCTI is a three-meter long linear device designed to inject compact torus (CT) into KTX at a high speed of over 100km/s. The tangential injection angle is...
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M. Vallar (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1008.pdfJT-60SA is large device (R_0/a=3.0/1.1) which will use neutral beam (NB) injection as the main actuator to reach the desired plasma temperature and performance[1]. In total, the NBI system provides 34MW of power, of which 10 (24) MW is injected at the energy of 500 (85) keV. The geometry features both parallel and...
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J.P. Graves (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1009.pdf
Analytic derivation and numerical calculation of pressure driven MHD instabilities in toroidal plasmas is notoriously difficult. Instability is determined by apparently weak effects in the toroidal metric tensor. A classical example is the m = n = 1 internal kink mode, where previous numerical and analytic results...
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V. Lukash (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1010.pdfAn increase of the poloidal flux expansion near the divertor target plates reduces the heat flux on the plates. A study has been performed with the goal to design and simulate with the DINA code [1] an ITER 15 MA DT scenario (Q = 10, Pfus = 500 MW) with a plasma configuration during the burn having a maximum expansion of...
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J. Morales (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1011.pdfPredicting plasma performance is an essential activity for assessing future campaigns in present day tokamaks as well as in future devices as ITER or JT-60SA. In particular, predictions for the ramp-up phase are of special importance, as successful plasmas in the flat-top phase critically depend on the initial...
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A.R. Polevoi (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1012.pdfThe parametric Operational Space (OS) for Steady-State (SS) operation [1] in ITER has been reassessed by global analysis taking into account the baseline design of the Neutral Beam Injection (NBI) and EC H&CD systems and their foreseen upgrades (up to P_NBI = 49.5 MW and with P_EC = 30 MW, where up to 40 MW upgrade is...
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O. Beeke (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1013.pdfPlasma shaping is known to affect the properties of micro instabilities that cause outwards radial transport of heat and particles in tokamaks. In particular, the elongation has been observed to have a stabilizing effect on the ion-temperature-gradient (ITG) instability in low-β plasmas, whilst increased triangularity...
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N. Carlevaro (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1014.pdfWith the aim of finding and validating reduced models able to reproduce the relevant features of the energetic particle interacting with the Alfvénic spectrum, we define a mapping procedure (based on the resonance rule) between the reduced radial profile of the burning plasma scenario and the velocity space of the...
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K. Kamiya (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1015.pdfIn this study, we analyzed the structure generation of the edge radial current (j_r) by means of Poisson's equation with a measured E_r data (CXRS diagnostic) in JT-60U NBI heating plasmas [1-4]. About 200 ms after the start of NBI heating, a slow L-H transition takes place, which evolves into a fully-developed H-mode...
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A. Bergmann (EPS 2019)7/12/19, 2:00 PMMCF
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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1016.pdfThe neoclassical impurity transport in the pedestal region of a tokamak plasma is studied with non-local guiding center particle simulations, employing the code HAGIS with a Monte Carlo collisions model. The simulations are done in two steps, assuming the trace limit for the impurity ions. First the parallel velocity of...
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R. Bielajew (EPS 2019)7/12/19, 2:00 PMMCF
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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1017.pdfI-mode is a naturally ELM-free improved confinement regime which exhibits high energy confinement and a temperature pedestal, but low particle confinement and a density profile similar to L-mode [1]. The weakly coherent mode (WCM) occurs in the pedestal region of Imode plasmas at both ASDEX Upgrade (AUG) and Alcator...
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J. Cheng (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1018.pdfIn the transition from low (L) to high (H) confinement regime a transport barrier usually develops in a narrow layer and so called pedestal of high temperature and density gradients forms at tokamak plasma edge [1]. The accumulation of energy and particles inside the pedestal normally leads to an explosive relaxation of...
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A.R. Field (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1019.pdfSustained ELMy H-mode operation at high heating power (~ 32 MW) in JET-ILW requires gas puffing to control radiation from high-Z impurities (W, Ni) by increasing their rate of removal by ELMs, as well as core ICRH heating to mitigate their accumulation and sweeping of the strike points to avoid overheating of the target...
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F. Jaulmes (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1020.pdfEdge transport barrier (ETB or pedestal) regime is often associated with transient relaxations (Edge Localized Modes or ELMs) of the plasma. These periodic bursts of particles and energy can significantly erode and damage the materials (eg. Tungsten, W) of the tokamak vessel. Any high-Z impurities remaining confined in...
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M. Sos (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1021.pdfElectron density and temperature profile measurements are important for magnetic confinement fusion research performed on tokamaks. One of the research areas these measurements help to understand is physics of edge transport barrier (pedestal) formation, which is closely related to plasma performance in the H-mode regime....
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B. Vanovac (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1022.pdfThe High confinement mode (H-mode) edge pedestal, a narrow region (~1.5 cm width) with steep pressure gradient just inside the last closed flux surface, is prone to various instabilities. Instabilities include intermittently occurring Edge Localised Modes (ELMs) but also other more continuous modes that occur in between...
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B.S. Victor (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1023.pdfRecent results on DIII-D show that low-field-side RMPs improve the robustness of discharges to high-Z impurity injection. Experiments were performed in H-mode ITER-baseline-shape discharges for three cases: 1. ELMy - q95 = 4.1, 2. RMP ELM-suppressed - q95 = 4.1, and 3. RMP with ELMs - q95 = 3.5. For each case above,...
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M. De Angeli (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1025.pdfDust in tokamaks is unlike to be mobilized prior to the beginning of plasma discharges, then dust presence in the vessel during the start-up phase of discharges is not considered an issue. Problems could arise due to the presence of magnetic dust [1,2,3] that are more likely to fly in the vessel volume during stat-up...
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E. Gilson (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1026.pdfLong periods of ELM quiescence <= 5sec were observed with BN injection into KSTAR ELMy H-modes with an innovative Impurity Powder Dropper (IPD) [1]. In addition, divertor D_α emission was substantially reduced with boron B injection into ELMy H-modes, indicating improved recycling control. In both cases, there was no...
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W. Gracias (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1027.pdfEdge simulations until recently focussed on simulating only the scrape-off layer (SOL) and including appropriate boundary conditions to the numerical domain to mimic effects like the presence of a separatrix on the inner radial boundary. To a large extent, flux-driven 3D simulations have had considerable success in...
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J. Wu (EPS 2019)7/12/19, 2:00 PMMCF
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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1028.pdfA beam emission spectroscopy (BES) diagnostic system has been developed on HL-2A tokomak. Combined with motional stark effect (MSE) diagnostics, the BES could assess the radial electric field and the safety factor, which plays an important role in plasma control and impurity transport processes. A Simulation of Spectra...
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M. Jia (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1029.pdfThe three-dimensional edge plasma transport with resonant magnetic perturbations (RMPs) in EAST is simulated with plasma responses being considered. This work is motivated by the significance of understanding plasma responses for optimizing edge localized mode (ELM) control and steady-state divertor flux control by...
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E. Marenkov (EPS 2019)7/12/19, 2:00 PM
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1030.pdfIntense heat loads on the plasma-facing components (PFC) of tokamaks during transient events such as Type I ELMs and disruptions may result in melting and evaporation of the materials. The evaporated impurity cloud ionizes and serves as a shield reducing heat loads on the PFC. Since accurate estimates of the power fluxes...
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C. Meineri (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1031.pdfTwo of the biggest challenges for future fusion reactors are the power dissipation and erosion of diverter targets. Alternative configurations such as Snowflake [1] (SF) and the Quasi-snowflake family (QSF), including Two Null nearby divertor [2] (TNND), have the aim of controlling and optimising the magnetic flux...
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F. Militello (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1032.pdfIn magnetic confinement devices, boundary turbulence is responsible for transporting plasma and energy from the well-confined region towards the material surfaces where it can severely harm reactor relevant machines. It is therefore essential to develop a solid understanding of the mechanisms behind the transport in the edge...
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D. Nina (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1033.pdfThe edge electron density at the midplane is a very important interface parameter between core (associated with fusion performance) and divertor plasma (able to control power exhaust). The separatrix density is also essential to assess the pedestal stability and has been observed to be related with the plasma energy...
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J. Dominguez-Palacios7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1034.pdfRecent experiments have shown that Edge Localized Modes (ELMs) can have a strong impact on the fast-ion population, causing significant losses and/or acceleration [1, 2]. These findings motivate a kinetic study of the interplay between fast-ions and ELMs. For this purpose, the 3D hybrid kinetic-MHD code MEGA [3] has been...
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T.H. Osborne (EPS 2019)7/12/19, 2:00 PMMCF
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1035.pdfThe Small Angle Slot (SAS) divertor installed on DIII-D combines high closure with small incidence angle to achieve detachment over the entire divertor at low density. Experiments on DIII-D comparing divertor detachment and other divertor characteristics of the SAS configuration to an otherwise identical open divertor...
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A. Pearce (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1036.pdf
As conceptual design options for a demonstration fusion power plant (DEMO) are explored it is important to understand the design space for possible non-ITER like design options. The power exhaust is a key design driver for a fusion power plant, and puts strong constraints on the size of the machine. One candidate for an...
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A.A. Pshenov (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1037.pdf
The power and particle exhaust are among the key problems to be solved for successful operation of ITER and DEMO [1]. The conventional solid plasma-facing component (PFC) solution suffers from numerous drawbacks such as material erosion and degradation under severe power, charged particle and neutron fluxes, possible...
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A. Punjabi (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1038.pdf
The nested magnetic surfaces that confine a fusion plasma can be designed to be bounded by a limiter or a divertor. For a limiter, confining surfaces extend until they intercept a part of the surrounding structure. For a divertor, an outermost confining magnetic surface exists which is well separated from the surrounding...
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G. Rubino (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1039.pdf
The operational conditions of DEMO require a high density and a high fraction of power radiated in the Scrape-Off Layer in order to fullfill the strict limits imposed by the material and the necessity to work in detached conditions. Indeed, almost the 95% of the input power must be radiated [1]. Various experiments in JET...
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S. Shu (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1040.pdf
Previous experimental results from the Experimental Advanced Superconducting Tokamak (EAST) have shown that the lower hybrid wave (LHW) can induce a 3D magnetic topology change at the plasma boundary, thus affect significantly the edge plasma transport and divertor heat flux distribution [1, 2]. To investigate further the...
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B. Tal (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1041.pdf
Edge localized modes (ELMs) are typically considered as major concerns for the main chamber wall. However, other smaller but more frequent events, so called inter-ELM bursts, which appear between type-I ELMs, could also harm the plasma-facing components. Although they only occasionally appear in the JET scrape-off layer in...
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I. Vasina (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1042.pdf
Liquid lithium is considered as a material for plasma facing components (PFCs) of fusion devices. Its properties have been widely studied at present. In particular, the lithium program of T-11M tokamak is focused on solving the technological problems of creating a stationary tokamak with plasma-facing components from...
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M. Wensing (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1043.pdf
The effect of the upcoming TCV divertor upgrade on the distribution of neutrals and the onset of detachment is studied using 2D transport simulations. The divertor upgrade is centered around the installation of a gas baffle to form a closed divertor chamber [1]. SOLPS-ITER simulations predict that the baffle geometry...
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F. Wilczynski (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1044.pdf
In magnetic confinement devices, the boundary turbulence is characterised by intermittent ejection of coherent filamentary structures. These filaments transport plasma from the well-confined core region, through the Scrape-Off Layer (SOL), towards the material surfaces. This results in increased plasma-wall interaction,...
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K. Wu (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1045.pdf
AST has implemented the feedback control of the radiated power to protect divertor target plates from overheating in H-mode long pulse discharges [1]. Since now, by the real-time control system it has been obtained a radiative fraction up to 40%, and it was found the neon (Ne) gas one of the best choices as the additional...
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G. Zhuang (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1046.pdf
Multifaceted asymmetric radiation as well as strong poloidal asymmetry of the electron density from the edge, dubbed as `MARFE', has been observed in high electron density Ohmically heated plasmas on J-TEXT tokamak. While the plasma density increasing further, it is found that the MARFE sometimes moves poloidally and...
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S. Okamura (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1047.pdf
CFQS is a new stellarator program proposed in China with the magnetic configuration of the quasi-axisymmetry. This program is an international joint project (NSJP) conducted by NIFS (National Institute for Fusion Science), Japan and SWJTU (Southwest Jiaotong University), Chengdu China. The number of toroidal period is 2...
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M. Roberto (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1048.pdf
To simulate magnetic configuration in tokamaks like ITER, we use a wires model consisting of electric currents in five parallel infinite wires to obtain double-null magnetic surfaces with specific choices of magnetic axis position, triangularity and elongation. This model reproduces quite well the ITER configuration and it...
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G. Avdeeva (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1049.pdf
The penetration depth of neutrals in fusion plasma determines the fueling efficiency of the applied puffing method. Experiments have proven higher efficiency of SMBI (supersonic molecular beam injection)[1] compare to GP (gas puffing), that can be explained by a high direct velocity of molecules and domination of...
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W. Lee (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1050.pdf
The Kubo number is estimated based on the correlation analysis of the density fluctuations measured by the 2D beam emission spectroscopy system in KSTAR. The Kubo number defined as an autocorrelation time of the fluctuating quantities normalized by the eddy turn over time characterizes significance of the nonlinear...
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S. Sridhar (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1051.pdf
Disruptions are a major threat to future tokamaks like ITER and beyond. In addition to heat and electromagnetic (EM) loads, disruptions also generate runaway electron (RE), tens of MeVs electron beams which may damage plasma facing. The current ITER disruption mitigation strategy is first to mitigate disruption heat/EM...
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G.G. Grenfell (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1052.pdf
The radial electric field (Er) is a crucial parameter to control transport both in tokamaks and in stellarators. Its local value is result of the interplay between neoclassical (NC) and turbulent mechanisms. In stellarators, the edge radial electric field changes its sign in a continuous manner during the electron (Er > 0)...
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Y. Li (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1053.pdf
Measurement of edge ion temperature is critical to understand the underlying physics of the island configuration effect on the plasma transport. Here, the Ti profile at the plasma boundary has been successfully measured on W7-X during the last experimental campaign OP1.2b by a retarding field analyzer (RFA) probe. The RFA...
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B. López-Miranda (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1054.pdf
Wall conditioning in TJ-II, is regularly performed by Glow Discharge deposition of B films and Li evaporation from ovens located inside the vacuum chamber [1]. In order to tests in-situ, real-time conditioning techniques, a Nd-YAG laser (normally used for Laser Blow-Off studies [2] and LIBS [3]) is used to ablate lithium...
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J. Fontdecaba (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1055.pdf
The majority ions present in Electron Cyclotron Resonance (ECR) heated plasmas in the stellarator TJ-II are heated through collisions with electrons. Since there is no direct heating of plasma ions in this device their thermal distribution is expected to be Maxwellian. However, during recent experiments in TJ-II a...
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K.J. McCarthy (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1056.pdf
Cryogenic pellet injection (PI) is a well established fuelling tool used on most mediumand large-sized magnetically confined plasma devices. PI technologies are mature and such systems are earmarked as critical items for future reactors. Nonetheless, despite significant progress over recent decades, a complete...
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N. Rust (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1057.pdf
This work presents details of the Wendelstein W7-X stellarator Neutral-Beam-Injector (NBI) system, and its effect on the beam dump, duct, heat efficiency and plasma current. During the last stellarator W7-X operation phase, the first of two NBI injectors (NI21) was taken into operation. It was equipped with two hydrogen...
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M. Zanini (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1058.pdf
The optimized stellarator W7-X generates its rotational transform by means of 70 superconducting coils. Therefore, no toroidal current is necessary for plasma confinement. Up to 10 gyrotrons can be used for electron cyclotron current drive (ECRH) and, in case of oblique beam injection, it is possible to drive a net current...
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A. Bencze (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1059.pdf
Early turbulence measurements in W7-X stellarator by means of poloidal correlation reflectometry [1] have revealed some important characteristics of turbulent density fluctuations such as the perpendicular ExB velocity and the decorrelation times in low density (0.6 10^19 - 2 10^19 m^-3) discharges. In a more recent study...
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A. Buzás (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1060.pdf
Various low frequency (~200 Hz) edge fluctuations were observed on the W7X stellarator. ELM-like events in ''high iota'' discharges[1] were seen on multiple diagnostics and an oscillation in the gradient of the light profile of the A-BES signal during FTM configurations. This profile variation is in strong correlation with...
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Z. Huang (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1061.pdf
Measurement of the edge radial profile of magnetic fluctuation is a basic and crucial method to investigate the edge turbulence and transport. A set of pick up coils, located in the combined probe head and mounted on the multi-purpose manipulator, has been used to measure the magnetic fluctuation in the scrape-off layer...
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C. Killer (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1062.pdf
In the Wendelstein 7-X Scrape-Off Layer (SOL), turbulent (radial) transport is assumed to play an important role for heat and particle transport to the divertor due to the generally long connection lengths of a few 100 m. The existence of large magnetic islands at the plasma edge results in a complex three-dimensional...
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A. Langenberg (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1063.pdf
This paper reports on trends for impurity transport with respect to different impurity species as observed in hydrogen plasmas of W7-X. Measurements of the impurity transport times τ_I [1] show a very similar impurity transport behaviour for a wide range of different impurities under the variation of the atomic number Z as...
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T. Ullmann (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1064.pdf
Since in magnetically confined fusion plasmas the evolution of transport barriers at the transition from the low to high confinement regime is accompanied by E × B shear flows, their interrelation with transport producing drift-wave (DW) turbulence has attracted much interest. In the Hasegawa-Mima model the redistribution...
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L. Vanó (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1065.pdf
The first absolute impurity density profiles of the optimised stellarator Wendelstein 7X (W7-X) plasma core will be presented and investigated under different operating scenarios. The profiles are derived from the Charge Exchange Recombination Spectroscopy (CXRS) diagnostic that observes the Neutral Beam Injection (NBI)...
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A. Hallenbert (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1066.pdf
An intriguing phenomenon, likely to be of relevance in future fusion devices operating at or near beyond the threshold of marginal ITG-stability, is the Dimits upshift, where close above the linear threshold stabilising zonal flow shear nearly complete suppress these modes. The general features of this phenomenon are...
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K. Hammond (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1067.pdf
Particle drifts are known to affect the fluxes of heat and particles to plasma-facing components of both tokamaks and stellarators. Here we present results from the first dedicated study of edge drift effects in W7-X scrape-off layer plasmas. In these experiments, similar discharges were repeated with forward and reversed...
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A. Casolari (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1068.pdf
Runaway electrons (RE) represent one of the main obstacles to the successful operation of ITER [1]. During plasma diruptions, the structure of magnetic surfaces is broken and large regions of stochastic magnetic field are created; however, the rapidly reforming magnetic flux tubes are able to trap RE for a long time [2]....
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3609. P5.1069 Inner versus outer ExB shear layer: an attempt to radially localize the L-H transitionM. Cavedon (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1069.pdf
The importance of the E × B flow shear in the transition from the low (L-) to the high (H-) confinement mode is well and widely appreciated [1]. At the edge of tokamaks, the E × B velocity profile shows two shear layers: the "inner" one is located within the confined region and is related to the ion pressure gradient while...
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J. Dominski (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1071.pdf
The neoclassical tungsten impurity transport is studied with the gyrokinetic neoclassical code XGCa [1,2] in whole volume JET plasma, from magnetic axis to scrape-off layer (SOL). Instead of simulating all 74 tungsten charge states, they are bundled and treated as several separate species. It is found, in a model JET...
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H. Du (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1072.pdf
The short wavelength ion temperature gradient (SWITG) driven instability in tokamak plasmas with hollow density profiles is numerically investigated by using the gyrokinetic integral eigenmode equation. It is found that for the hollow density profile (negative R / L_n , ), there exists a critical ion temperature gradient R...
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W. Guo (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1073.pdf
Turbulent impurity transport driven by parallel velocity shear (PVS) turbulence in hydrogen isotope plasmas is studied using the gyrokinetic theory in a slab configuration with weak magnetic shear. The quasi-linear impurity flux written in terms of diffusion and convection is analytically derived. It is found that PVS...
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A. Ho (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1074.pdf
The most widely accepted models for plasma turbulent transport are based on gyrokinetic (GK) theory, but the computational times of full nonlinear GK codes prohibit their use for applications such as experimental scenario optimization and control-oriented modelling. Reduced formulations of these equations have resulted in...
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D. Kouprienko (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1075.pdf
In contrast to theory expectations, the hydrogen isotope effect results in the improvement of tokamak energy confinement in numerous experiments as the hydrogen isotope mass increases, which has remained a long-standing puzzle [1]. This effect is beneficial and important for the success of Iter, where a fuel mixture of...
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N. Kumar (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1076.pdf
Transport of tungsten (W) in the central part of ITER is expected to be determined by neoclassical and turbulent processes, which strongly depend on the main ion density, temperature, and rotation profiles. Thus, to predict the W core transport behaviour, one needs to know the transport processes determining the density...
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T. Lan (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1077.pdf
In the common transport model, the anomalous transport is believed to be attributed to the plasma turbulence. The ExB shearing flow suppress the turbulence to reduce the radial
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transport. The formation of the transport barrier makes a very strong ExB shear to achieve the high confinement state (H-mode). The radial... -
M. Nurgaliev (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1078.pdf
The aim of this work is the determination of parametric dependencies of anomalous ion and electron heat conductivities in whole operational space of the T-10 tokamak. Verified experimental data base of plasma parameters, heat fluxes, and transport coefficients is made. It allow us to perform a background for transport...
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H. Cai7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1079.pdf
The evolution of neoclassical tearing modes (NTMs) in the presence of electrostatic drift wave turbulence is investigated. In contrast with anomalous transport effect induced by turbulence on NTMs, a new mechanism that turbulence-driven current can affect the onset threshold of NTMs significantly is suggested. Turbulence...
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J. Promping (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1080.pdf
This work uses an integrated predictive simulation code CRONOS to simulate plasma profiles of JET discharge. Simulations are carried out with ion and electron temperatures, electron density and toroidal velocity profiles predicted both individually and simultaneously. Core transport models used in these simulations is a...
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E.R. Solano (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1081.pdf
Much of the information on the isotope scaling of the L-H transition power threshold, P_LH, in JET is derived from early experiments in Hydrogen (H), Deuterium (D) and Tritium (T) with C wall (JET-C) [1]. More recent experiments have studied P_LH(H) and P_LH(D) in JET-C [2,3] and JET-ILW [4], and have shown considerable...
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A. Telnova (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1082.pdf
The presentation is devoted to particle and heat flux study in the Globus-M2 tokamak [1]. Globus-M2 is a spherical tokamak with the major radius R = 0.36 m and the minor radius a = 0.24 m (aspect ratio A = 1.5), and is the upgraded version of the Globus-M tokamak [2]. The upgrade allows increasing the plasma current I_P up...
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M. Valisa (EPS 2019)7/12/19, 2:00 PM
See the full abstract here: http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1083.pdf
Increasing the heating power in both baseline and hybrid JET H-mode scenarios modifies the edge kinetic profiles in a way that progressively reduces the neoclassical inward velocity of impurities [1]. Along this path JET approaches the situation expected in ITER where heavy impurities should be repelled at the H mode...
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G. Tardini (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1084.pdf
Heat transport in tokamaks is widely believed to be dominated by turbulence associated with gradient-driven modes. As a consequence, temperature profiles tend to clamp to a critical logarithmic gradient, weakly reacting to additional heating. The extent of this so-called "profile stiffness" is, however, different...
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X. Yang (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1085.pdf
W (Tungsten) accumulation in the core plasma could cause largely increased radiation because of its high cooling rate, which severely restricts long-pulse operation. In this context, WEST has achieved 30s L-mode pulses without any sign of W accumulation. The discharges were performed on the upper divertor in a full W...
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X. Zhang (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1086.pdf
Recent experiments on the EAST tokamak have extended the high-βN scenario towards the steady-state burning plasma regime by combination of NBI heating and LHW injection to obtain ~100% non-inductively-driven operation. By employing a very broad current profile, the negative magnetic shear leads to a high normalized...
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B. Luce (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1087.pdf
A tokamak has theoretically a toroidally symmetric magnetic field. However, the magnetic field is never perfectly homogeneous in the toroidal direction. The 2 most common reasons for non axisymmetric fields are engineering limitations and voluntary perturbations applied by additional coils for control purposes. The...
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T. Luda di Cortemiglia (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1088.pdf
The design of future fusion reactors and their operational scenarios require accurate estimates of the plasma confinement, which is a key parameter for the evaluation of the fusion performance. We are developing a new model that integrates different elements describing the main physics phenomena which determine plasma...
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A. Lyashenko (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1089.pdf
Turbulent dynamics of tokamak edge plasma related to convective motion of filamentary structures, or blobs, plays an important role in determining the heat and particle fluxes coming from core plasma to the first wall of the machine [1]. Combined with the problem of plasmasurface interaction and tritium retention in...
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A.V. Melnikov (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1090.pdf
An ExB drift poloidal rotation is now considered as an effective mechanism to suppress the plasma instabilities [1]. So, the direct radial electric field Er studies are important ingredient for understanding the role of E_r x B_t shear poloidal rotation in the turbulence suppression. In the -10 tokamak, the mean values...
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D. Réfy (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1092.pdf
The evolution of the edge plasma current in magnetically confined plasmas is identified as a critical parameter of Edge Localized Mode (ELM) destabilization. While the plasma pressure gradient, the other critical parameter, is routinely measured with high spatial and temporal resolution on fusion experiments, the...
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H. Raj (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1093.pdf
Formation of relativistic runaway electrons (REs) beam during plasma disruption, which can seriously damage the first wall, is a major threat to the safety of large tokamaks like ITER. In order to suppress the disruption-generated runaway beam, techniques such as massive gas injection, resonant magnetic perturbations...
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R.W. Schrittwieser (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1094.pdf
Blob transport is subject to intense study in fusion energy research for the understanding and prediction of particle and heat fluxes onto the plasma-facing components (PFC) [1]. Blobs originate around the separatrix at the outer midplane, forming filaments which expand and propagate in the parallel and, respectively,...
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A.Y. Sharma (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1095.pdf
Tokamak turbulence exhibits interaction on all length scales, but standard gyrokinetic treatments consider global scale flows and gyroscale flows separately, and assume a separation between these length scales. However, the use of a small-vorticity ordering [1, 2] allows for the presence of large, time-varying flows on...
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D. Smirnov (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1096.pdf
This paper continues our research on nonlinear low-frequency turbulent convection and associated anomalous cross-field transport processes of tokamak core plasmas [1]- [4]. Numerical simulations are performed with code CONTRA-C, which is developed in the frame of simplified cylindrical model for tokamaks [2]. The...
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A. Von Stechow (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1097.pdf
The Wendelstein 7-X superconducting stellarator at IPP Greifswald has a neoclassically optimized magnetic field, such that turbulent transport can be a major loss channel. Its variable three-dimensional field geometry is expected from analytical and numerical models to provide venues to modify both spatial localization...
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W. Wang (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1098.pdf
Global gyrokinetic simulations with self-consistent coupling of neoclassical and turbulent dynamics show that turbulence can significantly affect plasma self-driven mean current generation in tokamaks. The current amplitude, profile and phase space structure can all be modified. Turbulence can significantly reduce the...
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L. Guazzotto (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1099.pdf
A standard figure of merit for magnetic-confinement nuclear fusion experiments is expressed through the Lawson criterion [1]. The criterion gives the value for the "triple product" of plasma density, temperature and energy confinement time that must be reached in order for the plasma to ignite, i.e. to continue...
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M. Eder (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1100.pdf
A three-dimensional integrator for guiding center orbits of charged particles in toroidal fusion devices with 3D field geometry is described. The integrator uses a representation of the electromagnetic field by low order polynomials on a 3D tetrahedal grid and is intrinsically designed to preserve the total energy,...
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J.E. LÌ_pez (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1101.pdf
The study of plasma dynamics is the main tool for both the description and control of Tokamak devices for thermonuclear fusion systems, which has been carried out mainly by computational simulation techniques. The magnetohydrodynamic (MHD) equilibrium of the plasma is the starting point for the study of...
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C. Mazzotta (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1102.pdf
FTU offers the unique opportunity to explore a broad range of collisionality [1] expressed as ν_eff = 0.1 Zeff 〈ne〉 R / 〈Te〉^2.
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This work is devoted to study the dependence of the electron density profiles and peaking in a low collisionality regime, more interesting for comparison with other tokamaks [2]. With respect... -
R. Paccagnella (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1103.pdf
The RELAX device is a low aspect- ratio ( with R/a=2 where R and a are the major and minor radius of the torus) Reverse Field Pinch (RFP) in which on-axis resonant helical modes with m=1 and n=4 (m and n being the poloidal and toroidal mode numbers respectively) are observed during the so called Single Helical (SH)...
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3645. P5.1105 Design of neutron and gamma ray measurements for the start-up phase of the DTT tokamakM. Angelone (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1105.pdf
The Divertor Tokamak Test (DTT) facility, which is under design for construction in Frascati (Italy), will produce neutron yield up to 1.3*10^17 n/s at full power (H-mode scenario). This calls for an accurate design and selection of the 2.5 MeV neutron diagnostic systems and detectors which can give the fill...
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M. Issanova (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2001.pdf
Investigation of interaction processes of ion beams with dense plasmas is one of the key problems in physics of inertial confinement fusion driven by heavy ion beams [1]. The stopping power is an important quantity used to describe the interaction of particle beams with matter. In the field of particle-driven inertial...
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A.V. Branitskiy (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2002.pdf
The results of plasma compression studies of nested wire and fiber arrays with current flowing through them are presented in this work. Experiments were made on the Angara-51 installation with current up to 4 MA. The current implosion of nested arrays represents a unique opportunity to simulate the interaction of a...
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I.E. Golovkin (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2003.pdf
We present new features of PROPACEOS, a code that generates equation-of-state (EOS) and opacity tables for radiation-hydrodynamics and spectroscopic simulations. In addition to existing capabilities to produce tables for LTE and optically thin NLTE plasmas, these new features allow PROPACEOS to perform calculations...
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Z. Moldabekov (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2004.pdf
Advances on dense plasma diagnostics using X-ray scattering techniques [1] have allowed one to gain insight into the ionic dynamics at extreme conditions. As a result, properties such as the ion acoustic dispersion and corresponding sound velocity in dense plasmas and warm dense matter can be probed experimentally....
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B. Cho (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2005.pdf
The recent advent of the XFEL allowed us to follow ultrafast electron dynamics in the HED matter. We used femtosecond pulses from the PAL-XFEL to measure the ultrafast changes in the X-ray absorption of Cu nanofoil excited by intense laser pulses. Upon exposure to laser irradiation, significant portions of both the s/p...
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G. Kagan (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2006.pdf
Experiments are indicative of substantial kinetic effects in high-energy-density plasmas during the course of a spherical implosion. The effects appear as the plasma mean-free-path grows relative to the background scale making standard rad-hydro single-fluid description invalid. To understand their mechanics and...
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S. Kulkarni (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2007.pdf
SPECT3D is a collisional-radiative spectral analysis package designed to compute detailed emission, absorption, or x-ray scattering spectra, filtered images, XRD signals, and other synthetic diagnostics. The spectra and images are computed for virtual detectors by post-processing the results of hydrodynamics...
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M. Kucharik (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2009.pdf
Hydrodynamic simulations of laser-produced plasmas represent a useful tool both for theoreticians and experimentalists allowing them to investigate processes during laser-plasma interaction, which are often impossible to observe directly during the experiments. They allow not only interpretation of experimental...
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J. Nikl (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2010.pdf
The description of the energy transport processes in the laser plasma is crucial for capturing the dynamics of the lasertarget interaction relevant to shock ignition [1] and pre-pulses of ultra-intense lasers [2]. The diffusion approximation of the heat and radiation transport become inadequate even for the laser...
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C. Fiedler Kawaguchi (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2012.pdf
Hydrodynamic instabilities, such as the Rayleigh-Taylor (R.-T.) instability develop in high energy density, inertial confinement fusion (ICF) experiments. These instabilities degrade the implosion due to mixing of the fuel. We study R.-T. modes in ICF implosions in order to better understand how they evolve in time. To...
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S.H. Batha (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2014.pdf
Experimental, theoretical, simulation, and technological advances over the past 30 years are motivating a reassessment of the Magnetic Indirect Drive (MID) approach to Inertial Confinement Fusion (ICF). In this concept,1,2 a radiation source drives a hohlraum to temperatures required to implode a capsule symmetrically...
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V.N. Golovkina (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2015.pdf
The 3-D view factor code VISRAD is widely used in designing HEDP experiments at major laser and pulsed-power facilities, including NIF, OMEGA, OMEGA-EP, ORION, LMJ, Z, and PLX. It simulates target designs by generating a 3-D grid of surface elements, utilizing a variety of 3-D primitives and surface removal algorithms,...
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Z. Li (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2016.pdf
Laser-driven high-Z hohlraum is used to provide intense x-ray radiation source for driving the capsule implosion in indirect-dirve inertial confinement fusion (ICF). With the campaigns of hohlraum energetics and implosion physics in NIF, the lack of advanced knowledge on laser-hohlraum coupling process has shown the...
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S. Atzeni (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2017.pdf
Exploding pusher targets, i.e. gas-filled, large aspect-ratio shells, driven by a strong lasergenerated shock, are widely used as pulsed sources of neutrons and fast charged particles. Due to small convergence ratio, exploding pushers are little affected by fluid instabilities and are weakly sensitive to irradiation...
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G.C. Burdiak (EPS 2019)7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2018.pdf
We describe a newly commissioned pulsed-power machine, "M3", for driving high energy density physics experiments at First Light Fusion. 2.5 MJ of stored electrical energy is discharged in 2 us, generating currents of up to 14 MA into a low-inductance load. The primary purpose of M3 is to launch high velocity...
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M. Moreira (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2019.pdf
Beam hosing is a transverse beam-plasma instability that causes the centroid of a beam to oscillate with increasing amplitude and can therefore lead to the disruption of the beam as it propagates in plasma [1, 2, 3]. This instability can jeopardize those novel accelerator concepts which are based on plasma wakefields...
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R.A. Altuijri (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2020.pdf
A promising scheme for plasma wakefield acceleration is the hybrid plasma acceleration mechanism, which is experimentally connected to world-wide programs at various accelerator facilities. This scheme may lead to extremely high quality electron bunches, which can be used to drive ultrabright light sources such as free...
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B.F. Malaca (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2021.pdf
One of the most promising technologies to form the next generation of compact particle accelerators is plasma acceleration, providing accelerating distances up to 3 orders of magnitude shorter than conventional accelerators. Recent progress has been tremendous but improving beam quality still remains as a grand-challenge...
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R.A. Fonseca (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2022.pdf
The OSIRIS [1] Electromagnetic particle-in-cell (EM-PIC) code has been widely used in the numerical modeling of many astrophysical and laboratory scenarios. Since the release of version 4.0, the framework has been continuously developed to support multiple hardware architectures, and to extend the base algorithm, allowing...
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R. Calado (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.2023.pdf
Particle-in-Cell (PIC) codes are used in almost all areas of plasma physics, such as fusion energy research, plasma accelerators, space physics, ion propulsion, and plasma processing, and many other areas. In this work, we present the recent developments of the ZPIC educational code suite, a new initiative to foster...
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H. Lee (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3001.pdf
Studies on the plasma parameters and electron heating mechanism were investigated in the RF biased inductively coupled plasmas (ICPs), which are widely used and studied in various industrial plasma processes and laboratory research, by using careful plasma diagnostic techniques. In RF biased ICP (ICP+CCP), as the RF bias...
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N. Zorina (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3002.pdf
This work is devoted to the diagnostic of high frequency electrodeless light sources (HFEDL) for their use in high precision atomic absorption analyzers. The arsenic discharge is studied. The diagnostic technique consists of the line profiles measurements by means of Fourier transform spectrometer and Jobin Yvon SPEX 1000M...
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I.F. Punanov (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3003.pdf
In this work we study plasma beams generated by 70-kV 30-ns vacuum surface flashover discharge. The aim of the work was to compare parameters of particle flows at different values of discharge current and reveal the dependence of particle flow power on current. We used a pulsed generator with coaxial glycerol-filled...
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L.T. James (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3004.pdf
The ion drag force is one of the dominant forces determining the motion of dust particles in tokamak edge plasmas. We might expect that, in the same way that current onto a dust grain is suppressed by strong magnetic fields [1], the momentum flux will be also. However, the ion drag models employed by dust transport codes...
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L. Chen (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3005.pdf
The surface of tungsten powder with irregular shape was treated by thermal plasmas and the thermodynamics and dynamics behavior of powder particles in the plasma was monitored by the particle online monitor of DPV2000. The morphologies of the plasma plastic powders was observed by Scanning Electron Microscope (SEM). The...
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A. Petrovskaya (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3006.pdf
One of the current nuclear industry problems is irradiated reactor graphite deactivation during decommissioning of nuclear power plants, as well as findings of effective method for decontaminating of nuclear power equipment internal surfaces sedimented with radionuclides from reactor water during operation. Important...
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A.V. Ivchenko (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3007.pdf
The implementation of thermonuclear technology requires the development and formation of the reliable, long-lived nuclear fusion systems that will be able to guarantee the safe operation. Meanwhile, interaction plasma with divertor and the reactor first-wall elements leads to damage of their surfaces via erosion process...
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H. Chen (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3008.pdf
This study describes the specification, design and fabrication technology of the modified source spectrum filter for the combination of deuterium and halogen lamps light source system. The filter is modified and eliminated. The resulting Alpha deuterium line produces a smoother spectrum of light sources over a wide range...
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A. Shumikhin (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3009.pdf
In this work, using the chemical model of the atomic plasma "3+" proposed in [1], we present a joint calculation of the composition, equation of state and transport properties of metal vapors in warm dense matter regime within the unified approach The Helmholtz free energy of dense atomic metal vapors describe the mixture...
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A. Veselov (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3010.pdf
In spite of the well-studied microwave discharge and laser, the discharge in the beams of the THz frequency band remains practically unexplored, including the gas breakdown threshold. Nowadays, there is a significant progress in the study of the THz discharge, associated primarily with the development of sources of the...
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I. Vasileska (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3011.pdf
The divertor targets in tokamaks are constantly bombarded with high-energy neutral and charged particles and such violent events can pose a serious threat to the long-time resistance of the divertor materials. The wall erosion, caused by the bombardment, releases impurities, that migrate towards the bulk plasma and due to...
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M. Ugoletti (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3012.pdf
Neutral beam injectors (NBIs) are one of the most important additional heating devices both in present and in future nuclear fusion experiments. In order to heat the plasma at the high temperatures required, several critical aspects need to be fulfilled in the design of future NBI. In particular, one issue is the...
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S. Kuhn (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3013.pdf
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S. Schütt (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3014.pdf
Dusty plasmas typically contain one species of monodisperse dust particles. Experiments under microgravity conditions allow to study the dynamics of individual particles in three dimensionally extended systems. Adding a second species of monodisperse particles of different size allows to study phase separation processes....
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D. Fursa (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3015.pdf
Electron-impact excitation of the singlet states of H2 will either lead to dissociation through the excited singlet spectrum, or radiative decays to the vibrational levels of the ground electronic state. Decays to bound levels are one of the dominant processes by which vibrationally-excited H2 is formed in plasmas, which...
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I. Park (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3016.pdf
To understand dissociative recombination (DR) of positive ions at plasma-metallic walls is a key to control plasmas in fusion edge plasma, material processing and plasma bio-medicine. Especially, a product of DR would generate ozone (O3) as both positive effects (sterilization of germs) and negative effects (toxic to...
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N. El amine (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3018.pdf
A nonlinear model of void formation is proposed that includes the dust grain charge variation along with the grain-grain interaction and the effect of neutral density. It is found that the extension of the void decreases if the dust particulate charge is taken into account. Moreover, for bigger dust grains, it is seen that...
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T.I. Morozova (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3019.pdf
Waves and instabilities in a near-surface plasma above Phobos and Deimos are discussed. It is shown that the disturbance of the isotropy of the distribution function of electrons in dusty plasma above the surface of Mars satellites is associated with the movement of the solar wind relative to photoelectrons and charged...
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C. Duée7/12/19, 2:00 PM
See the full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3020.pdf
Forbidden in french constructions since 1997, asbestos remains present in most of the buildings constructed before this date. Thus, during work or in case of degradation, asbestos fibres can be emitted in air. The smaller the asbestos particles, the longer they stay ...
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V.G. Panchenko (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4001.pdf
The process of plasma radiation is studied when the transformation of an longitudinal Langmuir wave into the transverse electromagnetic wave occurs. The transformation takes place on turbulent plasma fluctuations in the presence of upper hybrid pump wave parametric instability. We consider the parametric decay of such wave...
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S. Changmai (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4002.pdf
We would be reporting about the preliminary results of the analysis using Particle In Cell (PIC) simulation on properties of photoemissive sheath in the presence of a magnetic field. Our present investigation reveals that the photoemission from a wall can induce electron twostream instability (ETSI) within the...
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M. Dwivedi (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4003.pdf
In the present work, the non-linear propagation of multi-Gaussian beam, consisting of coherent Gaussian beams with similar distribution [1], has been studied in collision-less plasma in the relativistic regime. We investigated the stimulated Raman scattering (parametric instability) of electromagnetic wave pulse and the...
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S. Punia (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4004.pdf
We have developed an analytical model to control the angular momentum of electrons trapped in ultra-relativistic laser-plasma interaction. The energy coupling from laser to plasma can be enhanced by using the foam target which regulates the near-critical density more efficiently in the medium. When laser is incident on the...
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V. Karakhtanov (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4005.pdf
Within the linear response theory in the formulation of Zubarev [1, 2] the modification of electron-ion and electron-electron correlation functions is made with the account of local field corrections in the dielectric function [3]. Recently the Chebyshev polynomial expansion of the Fermi distribution functions was...
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T. Vinci (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4006.pdf
SMILEI [1,2] is an open-source, collaborative Particle-In-Cell (PIC) code co-developed by plasma physicists and high-performance computing (HPC) specialists. Thanks to its userfriendly (Python) interface, built-in diagnostics and visualization tools, SMILEI can be used not only for research but also as a teaching...
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A. Paul (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4007.pdf
Supersolitons are qualitatively different solitary structures from conventional solitons in terms of the potential profile and the phase portrait of the corresponding dynamical system. It has been established that the existence of a soliton after the formation of double layer confirms the existence of a sequence of...
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X. Mushinzimana (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4008.pdf
Negative ion plasmas are observed in space and astrophysical environment (D and F layers of Earth's Ionosphere, Titan's atmosphere, Cometary comae) and in laboratory plasmas (e.g. plasmas processing reactors). In such plasmas, propagation of ion acoustic solitary waves have been observed experimentally in laboratory by...
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M. Khusroo (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4009.pdf
In a protoplanetary disk (PPD) system, the magneto-rotational instability (MRI) driven turbulence produces a strong electric field in the neutral co-moving frame when the ionization degree is low [2]. This electric field leads to plasma heating at some parts of a weakly ionized protoplanetary disk, which results in an...
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G. Inchingolo (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4010.pdf
The magnetorotational instability (MRI) is a crucial mechanism of angular momentum transport in several astrophysical scenarios, like accretion disks around black holes [1]. The MRI has been widely studied using MHD models and simulations, in order to understand the behavior of astrophysical fluids in a state of...
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C.R. Straub (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4011.pdf
Magnetic activity of distant objects can manifest itself in electron cyclotron emission. While it was detected from a large number of stellar objects (including pulsars) and brown dwarfs, not detection does not necessarily mean it does not happen. Being a highly directed radiation, it leaves the magnetospheres shaped as...
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J. Tsai (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4013.pdf
Under increasing driving and through modulation instability, the transition from the ordered wave to the weakly disordered wave state occurs in various nonlinear waves. The emergence of fluctuating topological defects at the sites with null amplitude and undefined phase leads to the name of defect-mediated turbulence (DMT)...
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W. Chen (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4014.pdf
In this work, wave turbulence transition from a stable plane wave to wave turbulence through intermediate weakly disordered state is investigated in self-excited 3D dust acoustic waves, composed of negatively charged particles suspended in low pressure RF discharges, through direct observing dust density fluctuations over...
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S. Valvis (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4015.pdf
Lower hybrid (LH) radio frequency (RF) waves are used in fusion tokamak devices to generate non-inductively toroidal currents. LH waves are effective in imparting toroidal momentum to electrons in the core of the confined plasma. Since the LH waves are generated by wave guide structures near the wall of a tokamak, the...
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U. Kumar (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4016.pdf
A currentless toroidal device (CTD) is one in which plasma is confined by the application of toroidal and vertical magnetic field only resulting in absence of a conventional effective rotational transform. Such devices provide a simple and well diagnosable test-bed for studies related to equilibrium, fluctuations and...
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J. Robertson (EPS 2019)7/12/19, 2:00 PM
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.4017.pdf
Understanding the behavior of plasma waves in mixed-species plasmas is important for explaining many observations seen in both space and laboratory plasmas. The addition of a second ion species in a magnetized plasma introduces new behavior in the propagation of waves in the ion cyclotron region, such as the ion-ion hybrid...
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