Results 31 to 40 of about 261 (113)

Implementation of a consistent fluid‐neutral model in SOLPS‐ITER and benchmark with EIRENE [PDF]

Contributions to Plasma Physics, 2018
In the quest for computationally affordable plasma edge transport simulations of reactor‐relevant plasmas, we consider fluid‐neutral models in this paper. To obtain good agreement with kinetic‐neutral models in charge‐exchange dominated regimes, model equations, transport coefficients, and boundary conditions have to be derived consistently from the ...
Blommaert, M., Dekeyser, W., Horsten, N., Boerner, P., Baelmans, M.   +4 more
openaire   +2 more sources

Exploring the edge operating space of fusion reactors using reduced physics models

Nuclear Materials and Energy, 2017
Reduced physics models within SOLPS have been used to explore the edge operating space of fusion reactors by building a database of simulations for various input powers and various combinations of impurity puffing.
D.P. Coster
doaj   +1 more source

First Monte‐Carlo modelling of global beryllium migration in ITER using ERO2.0

Contributions to Plasma Physics, Volume 60, Issue 5-6, June-July 2020., 2020
Abstract ERO2.0 is a recently developed Monte‐Carlo code for modelling global erosion and redeposition in fusion devices. We report here on the code's application to ITER for studying the erosion of the beryllium (Be) first wall armour under burning plasma steady state diverted conditions.
Juri Romazanov, Sebastijan Brezinsek, Andreas Kirschner, Dmitriy Borodin, Alina Eksaeva, Richard A. Pitts, Steven W. Lisgo, Himank Anand, Evgeny Veshchev, Vlad S. Neverov, Alexander B. Kukushkin, Andrey G. Alekseev, Christian Linsmeier   +12 more
wiley   +1 more source

Speed-up of SOLPS-ITER code for tokamak edge modeling [PDF]

Nuclear Fusion, 2018
Account of drifts and currents dramatically decreases the accessible time step for the integration of time dependent equations of SOLPS-ITER code for edge modeling. Running the code with sophisticated EIRENE Monte-Carlo model for neutrals and large number of fluid equations for multiple ion species makes the computation time unacceptably long.
Kaveeva, E., Rozhansky, V., Senichenkov, I., Veselova, I., Voskoboynikov, S., Bonnin, X., Coster, D.   +6 more
openaire   +4 more sources

A reduced model for the ITER divertor based on SOLPS solutions for ITER Q = 10 baseline conditions: B. A reduced model based on reversed-direction two point modeling

Nuclear Fusion, 2022
Edge codes such as SOLPS coupled to neutral codes such as EIRENE have become so comprehensive and sophisticated that they now constitute, in effect, ‘code-experiments’ that, as for actual experiments, can benefit from interpretation using simple models ...
P.C. Stangeby, J.D. Lore, R.A. Pitts, J.M. Canik, X. Bonnin   +4 more
doaj   +1 more source

Drifts, currents, and power scrape-off width in SOLPS-ITER modeling of DIII-D

Nuclear Materials and Energy, 2017
The effects of drifts and associated flows and currents on the width of the parallel heat flux channel (λq) in the tokamak scrape-off layer (SOL) are analyzed using the SOLPS-ITER 2D fluid transport code.
E.T. Meier, R.J. Goldston, E.G. Kaveeva, M.A. Makowski, S. Mordijck, V.A. Rozhansky, I.Yu. Senichenkov, S.P. Voskoboynikov   +7 more
doaj   +1 more source

SOLPS-ITER modeling of deuterium throughput impact on the ITER SOL plasma

Nuclear Materials and Energy, 2023
The impact of the ionization source in the ITER far SOL associated with main chamber deuterium puffing on the overall SOL performance is studied numerically using SOLPS-ITER modeling. It is found out that this source can have significant influence on the
E. Kaveeva, S. Makarov, I. Senichenkov, V. Rozhansky, I. Veselova, X. Bonnin, R.A. Pitts   +6 more
doaj   +1 more source

Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER

Nuclear Materials and Energy, 2019
The study aims to estimate the influence of machine scale size on the behavior of plasma with extrinsic seeded impurities in the scrape-off layer (SOL) and divertor.
Elizaveta Sytova, Richard A. Pitts, Elizaveta Kaveeva, Xavier Bonnin, David Coster, Vladimir Rozhansky, Ilya Senichenkov, Irina Veselova, Sergey Voskoboynikov, Felix Reimold   +9 more
doaj   +1 more source

Numerical implications of including drifts in SOLPS-ITER simulations of EAST

Physics of Plasmas
The inclusion of drifts in plasma edge codes like SOLPS-ITER is required to match simulation data with experimental profiles. However, this remains numerically challenging. In this paper, the effect of some numerical factors on the final plasma solution is investigated.
D. Boeyaert, S. Carli, W. Dekeyser, S. Wiesen, M. Baelmans   +4 more
openaire   +3 more sources

Modeling of tungsten impurity transport and distribution in EAST based on multi-fluid and kinetic Monte Carlo simulations

AIP Advances
In recent years, the materials of plasma facing components, such as divertor target plates, domes, and outer walls of tokamaks, such as ASDEX Upgrade, WEST, JET, EAST, and ITER, have been changed from carbon to tungsten because of its lower erosion and ...
Ziyang Wen, YiPing Chen, Ling Zhang
doaj   +1 more source