Results 41 to 50 of about 249 (122)

Novel SOLPS-ITER simulations of X-point target and snowflake divertors

Plasma Physics and Controlled Fusion, 2023
Abstract The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple X-point alternative divertor geometries such as snowflakes and X-point targets have great potential in reducing power loads ...
C Cowley, A Q Kuang, D Moulton, J D Lore, J Canik, M Umansky, M Wigram, S Ballinger, B Lipschultz, X Bonnin   +9 more
openaire   +2 more sources

First SOLPS‐ITER simulations of ASDEX Upgrade partially detached H‐mode with boron impurity: The missing radiation at the outer strike‐point region

Contributions to Plasma Physics, Volume 64, Issue 7-8, August-September 2024.
Abstract Partially detached H‐modes are the baseline regime for the future ITER operation. The ASDEX Upgrade partially detached H‐mode is modeled using the SOLPS‐ITER code with drifts enabled and compared with experimental data. For the first time, boron (B) impurity is simulated in the Scrape‐off layer (SOL) and divertor. A comparison between divertor
S. O. Makarov, D. P. Coster, T. Gleiter, D. Brida, M. Muraca, R. Dux, P. David, B. Kurzan, X. Bonnin, M. O'Mullane, ASDEX Upgrade Team   +10 more
wiley   +1 more source

A reduced model for the ITER divertor based on SOLPS solutions for ITER Q = 10 baseline conditions: A. identifying options for the control parameters

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

Global SOLPS-ITER and ERO2.0 coupling in a linear device for the study of plasma–wall interaction in helium plasma

Nuclear Fusion, 2023
Plasma–wall interaction (PWI) is a great challenge in the development of a nuclear fusion power plant. To investigate phenomena like erosion of plasma-facing components, impurity transport and redeposition, one needs reliable numerical tools for the ...
G. Alberti, E. Tonello, P. Carminati, A. Uccello, X. Bonnin, J. Romazanov, S. Brezinsek, M. Passoni   +7 more
doaj   +1 more source

Implementation of a 9-point stencil in SOLPS-ITER and implications for Alcator C-Mod divertor plasma simulations

Nuclear Materials and Energy, 2019
The SOLPS-ITER code suite is used worldwide for plasma edge modeling, the interpretation of experiments, as well as for the design of the ITER divertor. The numerical scheme of the plasma solver of the code, B2.5, is based on the assumption of perfectly ...
Wouter Dekeyser, Xavier Bonnin, Steven W. Lisgo, Richard A. Pitts, Brian LaBombard   +4 more
doaj   +1 more source

Towards assessment of plasma edge transport in Neon seeded plasmas in disconnected double null configuration in EAST with SOLPS-ITER

Nuclear Materials and Energy, 2021
Energy dissipation in the plasma edge is key for future tokamaks. The potential of neon as radiating seeding species in disconnected double null (DDN) configuration is assessed in EAST discharges in high confinement mode (H-mode).
D. Boeyaert, S. Wiesen, M. Wischmeier, W. Dekeyser, S. Carli, L. Wang, F. Ding, K. Li, Y. Liang, M. Baelmans   +9 more
doaj   +1 more source

Transport in the tokamak - reactor edge plasma with strong collisionality

Nuclear Materials and Energy, 2022
In detached divertor regimes, especially in future tokamak-reactors, plasma in the divertor is strongly collisional. When ion-ion and ion-neutral collision frequencies become comparable with the ion gyrofrequency, plasma transport is strongly affected by
V. Rozhansky, E. Kaveeva, I. Baranovsky, R.A. Pitts   +3 more
doaj   +1 more source

First SOLEDGE3X-EIRENE simulations of the ITER Neon seeded burning plasma boundary up to the first wall

Nuclear Materials and Energy
Boundary plasma simulations are essential to estimate expected divertor and first wall (FW) heat and particle loads on ITER during burning plasma operation.
S. Sureshkumar, N. Rivals, P. Tamain, X. Bonnin, R. Pitts, Y. Marandet, G. Ciraolo, H. Bufferand, G. Falchetto, N. Fedorczak, V. Quadri, M. Raghunathan, F. Schwander, E. Serre, R. Düll, N. Varadarajan   +15 more
doaj   +1 more source

Experimental and simulation study of helium plasma transport during ion cyclotron resonance heating in MPS-LD

Nuclear Fusion
The linear plasma devices (LPDs) can provide a good platform to experimentally simulate the divertor physics. MPS-LD is a new LPD, which uses ion cyclotron resonance heating (ICRH) to raise the ion temperature ( T _i ).
Changjiang Sun, Yanjie Zhang, Chaofeng Sang, Jintao Wu, Shuaishuai Gao, Yao Peng, Hao Wang, Chongyang Jin, Yue Wang, Qi Wang, Dezhen Wang   +10 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.
Boeyaert, D., Carli, S., Dekeyser, W., Wiesen, S., Baelmans, M.   +4 more
openaire   +3 more sources