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[HTML][HTML] In situ study of thermal shock damage to high-temperature ceramics
DE Cherepanov, LN Vyacheslavov, VA Popov… - Nuclear Materials and …, 2023 - Elsevier
New generations of fusion devices need alternative plasma-facing materials. The currently
approved material composition for the first wall and divertor of the ITER tokamak has a …
approved material composition for the first wall and divertor of the ITER tokamak has a …
Develo** solid-surface plasma facing components for pilot plants and reactors with replenishable wall claddings and continuous surface conditioning. Part A …
PC Stangeby, EA Unterberg, JW Davis… - Plasma Physics and …, 2022 - iopscience.iop.org
It is estimated that pilot plants and reactors may experience rates of net erosion and
deposition of solid plasma facing component (PFC) material of 10 3–10 5 kg yr− 1. Even if …
deposition of solid plasma facing component (PFC) material of 10 3–10 5 kg yr− 1. Even if …
Comprehensive screening of plasma-facing Materials for nuclear fusion
Plasma-facing materials (PFMs) represent one of the most significant challenges for the
design of future nuclear fusion reactors. Inside the reactor, the divertor will experience the …
design of future nuclear fusion reactors. Inside the reactor, the divertor will experience the …
Comprehensive new insights on the potential use of SiC as plasma-facing materials in future fusion reactors
The performance of silicon carbide as an alternative plasma facing material (PFM) was
studied at various irradiation conditions relevant to ion energies and fluxes of a fusion …
studied at various irradiation conditions relevant to ion energies and fluxes of a fusion …
[HTML][HTML] Computational investigation of incident ion angles and material erosion at rough graphite and silicon carbide divertor surfaces
We present a computational investigation of the dependence of material erosion on the
incident ion angle at rough graphite and silicon carbide divertor surfaces. Ion angle …
incident ion angle at rough graphite and silicon carbide divertor surfaces. Ion angle …
Electrode durability and sheared-flow-stabilized Z-pinch fusion energy
MC Thompson, SC Simpson, CJ Beers, J Dadras… - Physics of …, 2023 - pubs.aip.org
The sheared-flow-stabilized (SFS) Z-pinch concept is on a path to commercialization at Zap
Energy. Recent experiments on the Fusion Z-pinch Experiment (FuZE) and newly …
Energy. Recent experiments on the Fusion Z-pinch Experiment (FuZE) and newly …
In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection
Experiments have been conducted in the DIII-D tokamak to explore the in-situ growth of
silicon-rich layers as a potential technique for real-time replenishment of surface coatings on …
silicon-rich layers as a potential technique for real-time replenishment of surface coatings on …
Investigation of W-SiC compositionally graded films as a divertor material
W-SiC composite material is a promising plasma-facing material candidate alternative to
pure W due to the low neutron activation, low impurity radiation, and low tritium diffusivity of …
pure W due to the low neutron activation, low impurity radiation, and low tritium diffusivity of …
[HTML][HTML] SiC as a core-edge integrated wall solution in DIII-D
Silicon carbide (SiC) is a promising material for use in a fusion reactor due to its low
hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation …
hydrogenic diffusivity, high temperature strength and resilience under neutron irradiation …
Computational assessment on impurity sourcing and transport using high-temperature graphite and silicon carbide plasma-facing walls in a tokamak environment
Operating with hot tokamak plasma-facing components will be essential in fusion reactors to
maximize the thermal efficiency of the blanket. The SOLPS-ITER edge plasma code …
maximize the thermal efficiency of the blanket. The SOLPS-ITER edge plasma code …