Results 51 to 60 of about 21,104 (147)

Conclusive benchmark of SOLPS-ITER against the SOLPS4.3 ITER divertor design reference

open access: yesNuclear Fusion
The results of a detailed assessment of grid discretisation errors in SOLPS-ITER for ITER partially detached divertor solutions in a full metal wall configuration with neon seeding are presented.
S. Wiesen, X. Bonnin, R.A. Pitts
doaj   +1 more source

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

open access: yesAIP 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

Efficiency of thermal outgassing for tritium retention measurement and removal in ITER

open access: yesNuclear Materials and Energy, 2017
As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the risks of potential release during accidents, the inventory limit being set at 1kg.
G. De Temmerman   +9 more
doaj  

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