Results 1 to 10 of about 585 (174)
Investigation of helium exhaust dynamics at the ASDEX Upgrade tokamak with full-tungsten wall
Nuclear Fusion, 2023 An efficient removal of He ash by active pumping in future fusion devices is necessary to avoid fuel dilution and not degrade the core confinement properties. Therefore, a deep understanding of the underlying physics mechanisms is mandatory.
A. Zito +14 more
doaj +1 more source
Interpretive modeling of tungsten divertor leakage during experiments with neon gas seeding
Nuclear FusionMany existing and future tokamaks with tungsten divertors operate, or will operate, with low- Z impurity seeding, but the direct effect of these seeded impurities on tungsten Scrape-off-Layer (SOL) transport has not been explored in detail.
Matthew S. Parsons +8 more
doaj +1 more source
Improved erosion estimates for the STEP divertor
Nuclear Materials and EnergyNet tungsten erosion and deposition profiles are simulated for the outer and inner lower divertor of STEP, a spherical prototype fusion reactor targeting ∼ 2040.
A. Kirschner +6 more
doaj +1 more source
The interplay of controlling the power exhaust and the tungsten content in ITER
Nuclear Materials and Energy, 2017 The main elements defining the tungsten content of an ITER plasma, i.e. the gross erosion, the prompt redeposition and the transport in the H-mode edge transport barrier are reviewed and it is investigated, whether the low tungsten concentration limit in
R. Dux +5 more
doaj +1 more source
Innovative Tungsten Coatings for an Application in Modern and Future Fusion Devices
Metals, 2023 Tungsten is foreseen presently as the plasma-facing material for divertors in fusion power plants. In order to achieve durable operation of divertors of current fusion reactors, an efficient way of maintaining the divertor functionality is needed.
Tom Keller +4 more
doaj +1 more source
Heat Load Mitigation Studies in the W7‐X Stellarator Experiment
Contributions to Plasma Physics, EarlyView.ABSTRACT During the experiments at the stellarator Wendelstein 7‐X (W7‐X) with fully water‐cooled plasma‐facing components (PFC), including carbon‐fiber composite (CFC) divertor targets with a thermal load capability of 10 MW/m2, high performance was achieved.
Dirk Naujoks +11 more
wiley +1 more source
First SOLPS‐ITER Simulation Study of Japanese DEMO on Leakage of Seeded Ar Impurity
Contributions to Plasma Physics, EarlyView.ABSTRACT For JA DEMO, one of the grand challenges is efficiently handling the extreme power loads onto plasma‐facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets.
Hang Si +6 more
wiley +1 more source
Study of DIII-D tungsten erosion processes by using a carbon–tungsten mixed material model
Nuclear Materials and Energy, 2019 The tungsten erosion process for an H-mode discharge from the DIII-D Metal Rings Campaign is modeled using OEDGE and TRIM.SP. The OEDGE code is employed to calculate tungsten erosion between edge-localized modes (ELMs).
G.L. Xu +9 more
doaj +1 more source
Mathematical Analysis and Simulations of a Cancer Model With Interleukins and Delayed Immunotherapy
Mathematical Methods in the Applied Sciences, EarlyView.ABSTRACT A new system of delayed differential equations for tumor‐immune system interactions is proposed and studied. The system describes the interactions between tumor cells and the immune system at the most aggressive phase of cancer, where tumor cells have developed mechanisms from earlier stages to evade immune responses.
Laid Boudjellal +2 more
wiley +1 more source
Nuclear Materials and Energy, 2017 In the full-tungsten divertor qualification program at ITER Organization, macro-cracks, so called self-castellation were found in a fraction of tungsten monoblocks during cyclic high heat flux loading at 20MW/m2.
S. Panayotis +10 more
doaj +1 more source