Results 101 to 110 of about 249 (122)
Some of the next articles are maybe not open access.

Моделирование токамака «Глобус-М2» кодом SOLPS-ITER с кинетическим описанием нейтральных частиц

This work is devoted to modeling the Globus-M2 spherical tokamak using the SOLPS-ITER code with the EIRENE kinetic module and incorporating a large set of experimental data. In spherical tokamaks, due to the geometric features of this device type, the inner divertor plate experiences elevated thermal loads. The formation of a cold, dense plasma region (
openaire   +1 more source

DEMO physics challenges beyond ITER

Fusion Engineering and Design, 2020
Wolfgang Biel   +2 more
exaly  

ITER tungsten divertor design development and qualification program

Fusion Engineering and Design, 2013
Andrei Kukushkin   +2 more
exaly  

SOLPS-ITER modeling of SOL-divertor plasmas with different configurations in EAST

Nuclear Fusion, 2020
Y.P. Chen   +7 more
openaire   +1 more source

Design optimization of the ITER tungsten divertor vertical targets

Fusion Engineering and Design, 2018
Gregory De Temmerman
exaly  

Technological challenges of ITER diagnostics

Fusion Engineering and Design, 2005
George Vayakis
exaly  

Presentation of the New SOLPS-ITER Code Package for Tokamak Plasma Edge Modelling

Plasma and Fusion Research, 2016
Wouter Dekeyser   +2 more
exaly  

Investigation of TCV boundary plasmas in negative triangularity by SOLPS-ITER modelling [PDF]

open access: possible, 2023
Tonello E   +7 more
openaire   +1 more source

The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

Fusion Engineering and Design, 2014
Jerome Bucalossi   +2 more
exaly  

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