Results 21 to 30 of about 973 (141)
SOLPS-ITER simulation of W limiter start-up on ITER
The switch from beryllium (Be) to tungsten (W) first wall (FW) armor in the new ITER baseline Pitts et al (2025 Nucl. Mater. Energy 42 101854), Loarte (n.d. Plasma Phys. Control.
Y. Zhang +11 more
doaj +2 more sources
Validation of SOLPS-ITER simulations against the TCV-X21 reference case
This paper presents a quantitative validation of Scrape-Off Layer Plasma Simulation-ITER (SOLPS-ITER) simulations against the TCV-X21 reference case and provides insights into the neutral dynamics and ionization source distribution in this scenario.
Y. Wang +9 more
doaj +4 more sources
SOLPS-ITER simulations of the ITER divertor with improved plasma-facing component geometry
The ITER divertor design has been guided by SOLPS4.3 plasma boundary code simulations focused on baseline burning conditions at QDT = 10 which compose the majority of the existing ITER divertor scenario database.
Andrey Pshenov
exaly +3 more sources
First SOLPS-ITER modelling of an X-point radiator in ITER
For the first time, an X -point radiating (XPR) regime using neon (Ne) seed impurity has been obtained in ITER modelling with the SOLPS-ITER code, including fluid drifts.
A. Poletaeva +7 more
doaj +2 more sources
Benchmarking DIV1D on SOLPS-ITER simulations of TCV plasmas [PDF]
Derks, G.L. +6 more
core +2 more sources
A novel understanding of the role of plasma-molecular kinetics on divertor power exhaust [PDF]
During detachment, a buffer of neutral atoms and molecules builds up between the target and the ionising plasma. Collisions between the plasma and the molecules play an important role in the detachment process.
N. Osborne +17 more
doaj +2 more sources
Cross-code comparison of the edge codes SOLPS-ITER, SOLEDGE2D and UEDGE in modelling a low-power scenario in the DTT [PDF]
As reactor-level nuclear fusion experiments are approaching, a solution to the power exhaust issue in future fusion reactors is still missing. The maximum steady-state heat load that can be exhausted by the present technology is around 10 MW m-2 ...
Carati C. +10 more
core +1 more source
SOLPS-ITER modeling of divertor scenarios for EU-DEMO
We developed a first single null divertor scenario for EU-DEMO with the SOLPS-ITER code, including all charge states of D, He and Ar in the simulation and kinetic analysis of the neutral gas, but still leaving out drifts. Our results suggest that a partially detached divertor condition can indeed be obtained, with a corresponding peak heat flux on ...
F. Subba +3 more
openaire +2 more sources
Abstract New Grad–Zhdanov module is implemented in the SOLPS‐ITER code and applied to ITER impurity transport simulations. Significant difference appears in the helium transport due to improved parallel kinetic coefficients. As a result, 30% decrease of the separatrix‐averaged helium relative concentration is observed for the constant helium source and
S.O. Makarov +8 more
wiley +1 more source

