Multi-code estimation of DTT edge transport parameters

Balbinot, L.; Rubino, G.; Casiraghi, I.; Meineri, C.; Frassinetti, L.; Aucone, L.; Mantica, P.; Innocente, P.; Wigram, M.

doi:10.1016/j.nme.2022.101350

Cited by 5 publications

(8 citation statements)

References 16 publications

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“…Edge mode has been done with the 2D fluid code SOLEDGE2D [12] using the Monte Carlo code EIRENE [26] for neutrals. Transport values have been estimated for DTT by modeling JET and C-mod experiments and extrapolating to match the heat flux decay length with the Eich's scaling law [27] applied to DTT, as described in [28]. Drifts are not included in the modeling, because they often cause a considerable slow-down of the code convergence, without adding serious physical details, at least at the accuracy level needed for this analysis.…”

Section: Scrape-off-layer Simulationsmentioning

confidence: 99%

Kinetic modeling of the plasma–wall interaction in the DTT divertor region

Cichocki,

Innocente,

Sciortino

et al. 2024

Plasma Phys. Control. Fusion

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A precise estimate of the local energy fluxes and erosion profiles at the divertor monoblocks of a fusion reactor requires a kinetic modeling of the plasma-wall interaction. Here, a two-dimensional Particle-in-Cell code is used to quantify the particle and energy fluxes and ion impact distribution functions across the divertor monoblocks of the ``Divertor Tokamak Test'' reactor, focusing on poloidal gaps with toroidal beveling. The considered critical locations are close to the strike points at both Inner and Outer Vertical Targets. A worst-case scenario for particle fluxes corresponding to attached plasma conditions and featuring a single-null magnetic configuration is assumed. The separate and cumulative effects of including electron wall emission and ions/electrons collisions with a background neutral gas (recycled at the walls) are also assessed. It is found that a non-negligible energy flux affects the shadowed regions of the monoblocks, especially when accounting for collisions, and that the ion impact distribution functions are strongly influenced by the considered kinetic effects, with important implications on the induced sputtering yield.

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Section: Scrape-off-layer Simulationsmentioning

confidence: 99%

Kinetic modeling of the plasma–wall interaction in the DTT divertor region

Cichocki,

Innocente,

Sciortino

et al. 2024

Plasma Phys. Control. Fusion

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“…To enhance the reliability of our modelling predictions, matching as well as possible the key parameters between core and SOL simulations is an essential aspect. Firstly, an investigation work about the SOL parameter ranges in existing tokamaks (C-mod and JET), described in [18], was done to establish the best set of input parameters for DTT.…”

Section: The Dtt Integrated Modellingmentioning

confidence: 99%

“…Particularly, the SOL modelling takes as input from the core modelling the values of power flowing outward from the separatrix and its splitting between the electron and the ion channels, while in the core modelling the impurity contents and the plasma pressure boundary conditions are set based on separatrix values calculated by the SOL modelling. Moreover, the core modelling transport profiles were used in [18] to better tune specific DTT transport coefficients to be used in the SOL modelling of DTT scenarios [12].…”

Section: The Dtt Integrated Modellingmentioning

confidence: 99%

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

Casiraghi

Mantica

Ambrosino

et al. 2023

Plasma Phys. Control. Fusion

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Deuterium plasma discharges of the Divertor Tokamak Test facility (DTT) in diﬀerent operational scenarios have been predicted by a comprehensive ﬁrst-principle based integrated modelling activity using state-of-art quasi-linear transport models. The results of this work refer to the updated DTT conﬁguration, which includes a device size optimisation (enlargement to R0 = 2.19 m and a = 0.70 m) and upgrades in the heating systems. The focus of this paper is on the core modelling, but special attention was paid to the consistency with the SOL parameters required to achieve divertor plasma detachment. The compatibility of these physics-based predicted scenarios with the electromagnetic coil system capabilities was then veriﬁed. In addition, ﬁrst estimates of DTT sawteeth and of DTT ELMs were achieved.

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“…The boundary conditions of electron and ion temperatures T e = T i = 130 eV, electron density n e = 8 × 10 19 m −3 , plasma current I p = 5.5 MA have been imposed at the separatrix and kept constant during the running time. These values have been chosen in order to operate in fully detached plasma conditions [4] based on SOL studies performed for DTT [3][4][5].…”

Section: Multi-channel Integrated Modelling Setup For Dtt Full Power ...mentioning

confidence: 99%

“…The neutral influx is assumed poloidally symmetric. The study of the impact of the location of the gas pumping on the fuelling efficiency has been performed by the SOL modelling using appropriate 3D-codes [3][4][5]. The work is ongoing and different positions are under investigation.…”

Section: Multi-channel Integrated Modelling Setup For Dtt Full Power ...mentioning

confidence: 99%

Core transport modelling of the DTT full power scenario using different fuelling strategies

Baiocchi,

Aucone,

Casiraghi

et al. 2023

Nucl. Fusion

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A theory-based integrated modelling work of plasma response to deuterium fuelling in the new Divertor Tokamak Test facility (DTT) is performed, using the transport code JETTO with the quasi-linear anomalous transport model QuaLiKiz for the core region. The full power DTT scenario E1 is investigated. It is characterized by 28.8 MW of Electron Cyclotron Resonance Heating (ECRH), 10 MW of Neutral Beam Injection and 6 MW of Ion Cyclotron Resonance Heating to the plasma. Plasma density and temperature profile evolution is calculated using two different fuelling methods, gas puffing and pellet injection, and two different seeding gases, argon and neon. With gas puffing the neutral flux at the separatrix needed to sustain the desired pedestal density level exceeds the feasibility limits of the pumping system, regardless of the type of impurity introduced, thus making the use of pellets mandatory. The simulations performed with pellet injection as fuelling method predict that the pedestal density is well sustained with realistic parameters foreseen for the DTT pellet injector. Strong dependence of the core density on the EC power deposition profile is found. TEM dominance, low outward flux and strongly hollow density in the inner core region are foreseen with central peaked EC power deposition profile. ITG dominance, inward flux and robust density sustainment on the whole radial interval are predicted for spread EC power deposition, though with central density close to the EC limit and with peaked impurity densities. An intermediate deposition extension is found to sustain the whole density profile and to obtain flatter core densities, as previously predicted for the reference full power DTT scenario by fixed pedestal simulations. The EC deposition is negligibly modified by refraction changes both during a single pellet cycle and after several pellet cycles, indicating full compatibility between the EC system and the pellet injection system.

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Multi-code estimation of DTT edge transport parameters

Cited by 5 publications

References 16 publications

Kinetic modeling of the plasma–wall interaction in the DTT divertor region

Kinetic modeling of the plasma–wall interaction in the DTT divertor region

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

Core transport modelling of the DTT full power scenario using different fuelling strategies

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