See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1002.pdf
The 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1003.pdf
Disruptions 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1011.pdf
Predicting 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1012.pdf
The 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1014.pdf
With 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1016.pdf
The 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1017.pdf
I-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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1019.pdf
Sustained 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1020.pdf
Edge 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1022.pdf
The 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1023.pdf
Recent 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1025.pdf
Dust 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...
See full abstract here:
http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1027.pdf
Edge 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1031.pdf
Two 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1032.pdf
In 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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http://ocs.ciemat.es/EPS2019ABS/pdf/P5.1035.pdf
The 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...
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...
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...
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...
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...
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,...
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)...
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...
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...
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...
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...
See full abstract here http://ocs.ciemat.es/EPS2019ABS/pdf/P5.3013.pdf
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...
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...
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...
