Results 71 to 80 of about 96,750 (196)

Geometry and performance of the solid tungsten divertor row in JET

open access: yes, 2010
At JET new plasma-facing components for the main chamber wall and the divertor are being designed and built to mimic the expected ITER plasma wall conditions in the deuterium-tritium operation phase.
Riccardo, V.   +7 more
core   +1 more source

Designing Polymer Nanocomposites for X‐Ray Shielding: Mechanisms, Architectures, and Scalable Processing

open access: yesAdvanced Engineering Materials, Volume 28, Issue 15, 5 August 2026.
This review highlights advances in lightweight, lead‐free polymer nanocomposites for diagnostic X‐ray shielding. By linking filler chemistry, dispersion, architecture, and photon interaction mechanisms, it establishes structure–performance relationships guiding material design.
Aklilu G. Messele   +2 more
wiley   +1 more source

Magnesium‐Based Transient Bioelectronics, Bio‐Optics and Bio‐Scaffolds

open access: yesAdvanced Functional Materials, Volume 36, Issue 67, 20 August 2026.
This paper reviews the state of the art and recent advances in magnesium‐based thin‐film, foils, and scaffolds for applications in transient bio‐optics, bioelectronics and tissue engineering. The design principles, fabrication methods, material properties, and integration strategies are discussed in detail.
Massimo Mariello, Yves Leterrier
wiley   +1 more source

Suppression of tungsten accumulation during ELMy H-mode by lower hybrid wave heating in the EAST tokamak

open access: yesNuclear Materials and Energy, 2017
EAST tokamak has been equipped with upper tungsten divertor since 2014. The tungsten accumulation has been often observed in NBI-heated H-mode discharges suggesting deleterious tungsten confinement in the plasma core.
L. Zhang   +20 more
doaj   +1 more source

Detachment control in KSTAR with Tungsten divertor

open access: yes
KSTAR has recently undergone an upgrade to use a new Tungsten divertor to run experiments in ITER-relevant scenarios. Even with a high melting point of Tungsten, it is important to control the heat flux impinging on tungsten divertor targets to minimize sputtering and contamination of the core plasma.
Gupta, Anchal   +9 more
openaire   +2 more sources

Mathematical Analysis and Simulations of a Cancer Model With Interleukins and Delayed Immunotherapy

open access: yesMathematical Methods in the Applied Sciences, Volume 49, Issue 12, Page 13946-13970, August 2026.
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

Dust collection after the high fluence campaign of the WEST tokamak

open access: yesNuclear Materials and Energy
For Phase 2 of WEST, the lower divertor was entirely equipped with actively cooled ITER grade plasma-facing units made of chains of tungsten beveled monoblocks. In this configuration, dust particles were collected in 2023, after the first plasma campaign
C. Arnas   +8 more
doaj   +1 more source

Threshold Currents of Vacuum Arcs With Tungsten and Copper Cathodes

open access: yesHigh Voltage, Volume 11, Issue 4, Page 906-915, August 2026.
ABSTRACT This paper presents the results of an experimental study aimed at determining the threshold current for triggering a vacuum arc discharge, the probability of arc ignition and the average arc operation time depending on the current for tungsten and copper electrodes.
P. S. Mikhailov   +4 more
wiley   +1 more source

Design Study of LHD Helical Divertor and High Temperature Divertor Plasma Operation

open access: yes, 1992
"The Large Helical device (LHD), now under construction is a Heliotron/torsatron device with a closed divertor system. The LHD divertor magnetic structure has been studied in detail.
Noda, N.   +16 more
core  

ELM heat flux in the ITER divertor [PDF]

open access: yes, 1998
Edge-Localized-Modes (ELMs) have the potential to produce unacceptable levels of erosion of the ITER divertor. Ablation of the carbon divertor target will occur if the surface temperature rises above about 2,500 C.
Herrmann, A.   +9 more
core  

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