Turnitin
降AI改写
早检测系统
早降重系统
Turnitin-UK版
万方检测-期刊版
维普编辑部版
Grammarly检测
Paperpass检测
checkpass检测
PaperYY检测
Perspectives on multiscale modelling and experiments to accelerate materials development for fusion
Prediction of material performance in fusion reactor environments relies on computational
modelling, and will continue to do so until the first generation of fusion power plants come on …
modelling, and will continue to do so until the first generation of fusion power plants come on …
Recent progress of radiation response in nanostructured tungsten for nuclear application
H Xu, LL He, YF Pei, CZ Jiang, WQ Li, XH **ao - Tungsten, 2021 - Springer
Engineering materials for nuclear reactors exposed to high-dose irradiation breed various
radiation damage, leading to performance degradation of materials, which seriously limits …
radiation damage, leading to performance degradation of materials, which seriously limits …
The evolution of dislocation loop and its interaction with pre-existing dislocation in He+-irradiated molybdenum: in-situ TEM observation and molecular dynamics …
Y Li, G Ran, Y Guo, Z Sun, X Liu, Y Li, X Qiu, Y **n - Acta Materialia, 2020 - Elsevier
In-situ TEM observation and molecular dynamics simulation were used to investigate the
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …
Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: Microstructure, effect of dpa rate, temperature, and grain size
Displacement damage, through heavy ion irradiation was studied on two tungsten grades
(coarse grained tungsten (CGW) and nanocrystalline and ultrafine grained tungsten (NCW)) …
(coarse grained tungsten (CGW) and nanocrystalline and ultrafine grained tungsten (NCW)) …
Parameter-free quantitative simulation of high-dose microstructure and hydrogen retention in ion-irradiated tungsten
Hydrogen isotopes are retained in plasma-facing fusion materials, triggering hydrogen
embrittlement and changing tritium inventory as a function of exposure to neutron irradiation …
embrittlement and changing tritium inventory as a function of exposure to neutron irradiation …
Unprecedented irradiation resistance of nanocrystalline tungsten with equiaxed nanocrystalline grains to dislocation loop accumulation
Nanocrystalline metals are often postulated as irradiation tolerant materials due to higher
grain boundary densities. The efficiency of these materials in mitigating irradiation damage …
grain boundary densities. The efficiency of these materials in mitigating irradiation damage …
[HTML][HTML] Simulated TEM imaging of a heavily irradiated metal
Abstract We recast the Howie–Whelan equations for generating simulated transmission
electron microscope (TEM) images, replacing the dependence on local atomic …
electron microscope (TEM) images, replacing the dependence on local atomic …
Orientation dependence of shock-induced change of habit plane for the 1/2< 111> dislocation loop and plasticity in tungsten
Tungsten (W) is a promising candidate material for future fusion reactors. The shock waves
generated under high-energy neutron radiation can lead to the formation of prismatic …
generated under high-energy neutron radiation can lead to the formation of prismatic …
Dislocation structure of tungsten irradiated by medium to high-mass ions
B Wielunska, T Płociński, T Schwarz-Selinger… - Nuclear …, 2022 - iopscience.iop.org
Single crystalline tungsten was irradiated by the medium-mass ion Si with 7.5 MeV and high
mass-ion W with 20.3 MeV up to a calculated peak damage level of 0.04 dpa and 0.5 dpa …
mass-ion W with 20.3 MeV up to a calculated peak damage level of 0.04 dpa and 0.5 dpa …
Microstructure evolution and lead-bismuth eutectic corrosion behavior of 11Cr1Si ferritic/martensitic steel after proton irradiation
Q Chen, H Liu, J Yang, C Zhu, W Zhang… - Journal of Nuclear …, 2022 - Elsevier
The effect of proton irradiation fluence on microstructure evolution and lead-bismuth eutectic
(LBE) corrosion behavior of 11Cr1Si ferritic/martensitic (F/M) steels was investigated. The …
(LBE) corrosion behavior of 11Cr1Si ferritic/martensitic (F/M) steels was investigated. The …