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Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …
Materials for sustainable nuclear energy: a European strategic research and innovation agenda for all reactor generations
Nuclear energy is presently the single major low-carbon electricity source in Europe and is
overall expected to maintain (perhaps eventually even increase) its current installed power …
overall expected to maintain (perhaps eventually even increase) its current installed power …
Ductile to brittle transition temperature of advanced tungsten alloys for nuclear fusion applications deduced by miniaturized three-point bending tests
A large campaign of characterization of the ductile to brittle transition temperature (DBTT)
and microstructure has been performed on several commercial and lab-scale pure tungsten …
and microstructure has been performed on several commercial and lab-scale pure tungsten …
Ultrahigh strength, thermal stability and high thermal conductivity in hierarchical nanostructured Cu-W alloy
JG Ke, R Liu, ZM **e, LC Zhang, XP Wang, QF Fang… - Acta Materialia, 2024 - Elsevier
The wider application of copper alloys is challenged due to their relatively low strength and
thermal stability. Here we report a nano-reinforcement dispersion strategy to achieved an …
thermal stability. Here we report a nano-reinforcement dispersion strategy to achieved an …
Development of the material property handbook and database of CuCrZr
K Zhang, E Gaganidze, M Gorley - Fusion Engineering and Design, 2019 - Elsevier
This paper covers the initial progress on the development of material property handbook
(MPH) of baseline CuCrZr, within the Materials Engineering Data and Design Integration …
(MPH) of baseline CuCrZr, within the Materials Engineering Data and Design Integration …
Dislocation dynamics simulation of thermal annealing of a dislocation loop microstructure
Thermal evolution and elevated temperature annealing of the dislocation microstructure of
an irradiated metal, represented by an ensemble of elastically interacting interstitial …
an irradiated metal, represented by an ensemble of elastically interacting interstitial …
Nonuniversal structure of point defects in face-centered cubic metals
Using ab initio density function theory calculations, we have determined the structure of self-
interstitial atom (SIA) defects in the most commonly occurring face-centered cubic (FCC) …
interstitial atom (SIA) defects in the most commonly occurring face-centered cubic (FCC) …
Effects of swift heavy ions at different fluencies on WC-6Co hard metal alloy
Tungsten carbide hard metal alloy with 6% by weight cobalt was studied before and after
irradiation at different fluencies with 167 MeV 132 Xe ions. Raman spectroscopy, X-ray …
irradiation at different fluencies with 167 MeV 132 Xe ions. Raman spectroscopy, X-ray …
Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys
D Terentyev, M Rieth, G Pintsuk, J Riesch… - Nuclear …, 2022 - iopscience.iop.org
The present contribution highlights results of the recent irradiation campaigns applied to
screen mechanical properties of advanced tungsten and copper-based materials—main …
screen mechanical properties of advanced tungsten and copper-based materials—main …
STEP—on the pathway to fusion commercialization
H Wilson, I Chapman, T Denton, W Morris… - … Fusion Energy: How …, 2020 - iopscience.iop.org
Entering its final construction phase, the international fusion experiment, ITER, will
demonstrate much of the science and technology for net fusion gain. In parallel, major …
demonstrate much of the science and technology for net fusion gain. In parallel, major …