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Results of high heat flux tests of tungsten divertor targets under plasma heat loads expected in ITER and tokamaks
VP Budaev - Physics of Atomic Nuclei, 2016 - Springer
Heat loads on the tungsten divertor targets in the ITER and the tokamak power reactors
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …
The geometry of the ICRF-induced wave–SOL interaction. A multi-machine experimental review in view of the ITER operation
As part of ITPA-Integrated Operational Scenario activities, this contribution reviews recent
experimental characterizations of radio-frequency (RF)-induced scrape-off layer (SOL) …
experimental characterizations of radio-frequency (RF)-induced scrape-off layer (SOL) …
Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST
A new lower tungsten divertor has been developed and installed in the EAST
superconducting tokamak to replace the previous graphite divertor with power handling …
superconducting tokamak to replace the previous graphite divertor with power handling …
[HTML][HTML] Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER
S Brezinsek, JET-EFDA contributors - Journal of nuclear materials, 2015 - Elsevier
Abstract The JET ITER-Like Wall experiment (JET-ILW) provides an ideal test bed to
investigate plasma-surface interaction (PSI) and plasma operation with the ITER plasma …
investigate plasma-surface interaction (PSI) and plasma operation with the ITER plasma …
Conceptual design study for heat exhaust management in the ARC fusion pilot plant
The ARC pilot plant conceptual design study has been extended beyond its initial scope [BN
Sorbom et al., FED 100 (2015) 378] to explore options for managing∼ 525 MW of fusion …
Sorbom et al., FED 100 (2015) 378] to explore options for managing∼ 525 MW of fusion …
Material testing facilities and programs for plasma-facing component testing
Component development for operation in a large-scale fusion device requires thorough
testing and qualification for the intended operational conditions. In particular environments …
testing and qualification for the intended operational conditions. In particular environments …
Impact of nitrogen seeding on confinement and power load control of a high-triangularity JET ELMy H-mode plasma with a metal wall
C Giroud, GP Maddison, S Jachmich, F Rimini… - Nuclear …, 2013 - iopscience.iop.org
This paper reports the impact on confinement and power load of the high-shape 2.5 MA
ELMy H-mode scenario at JET of a change from all carbon plasma-facing components to an …
ELMy H-mode scenario at JET of a change from all carbon plasma-facing components to an …
Erosion, screening, and migration of tungsten in the JET divertor
S Brezinsek, A Kirschner, M Mayer… - Nuclear …, 2019 - iopscience.iop.org
The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles,
determines the lifetime of plasma-facing components as well as impacting on plasma …
determines the lifetime of plasma-facing components as well as impacting on plasma …
ELM-induced transient tungsten melting in the JET divertor
The original goals of the JET ITER-like wall included the study of the impact of an all W
divertor on plasma operation (Coenen et al 2013 Nucl. Fusion 53 073043) and fuel retention …
divertor on plasma operation (Coenen et al 2013 Nucl. Fusion 53 073043) and fuel retention …
ELM-resolved divertor erosion in the JET ITER-like wall
Tungsten erosion in H-mode plasmas is quantified in the outer divertor of the JET ITER-Like
Wall environment with optical emission spectroscopy on the 400.9 nm atomic neutral …
Wall environment with optical emission spectroscopy on the 400.9 nm atomic neutral …