Keywords: High intensity neutron source; Target assembly; Thermo-structural analysis; Li target; IFMIF; F82H;
مقالات ISI (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
Keywords: First wall; F82H; Tungsten coatings; Gas-driven permeation; Trapping effects;
Keywords: SP creep test; SPC; SSTT; F82H;
Keywords: SP creep test; SPC; SSTT; FEA; F82H;
The effect of γ-ray irradiation on deuterium permeation through reduced activation ferritic steel and erbium oxide coating
Keywords: Tritium; Permeation; γ-ray; Irradiation; F82H; Erbium oxide;
Instability of MX and M23C6 type precipitates in F82H steels under 2.8Â MeV Fe2+ irradiation at 673Â K
Keywords: F82H; Ion irradiation; Precipitates; Instability;
Erosion and morphology changes of F82H steel under simultaneous hydrogen and helium irradiation
Keywords: F82H; Helium; Hydrogen; Erosion; Surface modification; Simultaneous irradiation;
Bi-directional hydrogen isotopes permeation through a reduced activation ferritic steel F82H
Keywords: First wall; F82H; Gas- and plasma-driven permeation; Transport parameters; Isotopic effect;
Microstructure and mechanical property in heat affected zone (HAZ) in F82H jointed with SUS316L by fiber laser welding
Keywords: Fiber laser welding; Dissimilar joint; F82H; M23C6; HAZ; Nano-indentation hardness;
Helium trapping in carbide precipitates in a tempered F82H ferritic–martensitic steel
Keywords: F82H; TEM; APT; Ion irradiation; Helium
Effect of induced damage on hydrogen isotope retention of F82H with impurity layer
Keywords: F82H; Oxide layer; Radiation damage; Hydrogen isotope retention
Evaluation of local deformation behavior accompanying fatigue damage in F82H welded joint specimens by using digital image correlation
Keywords: F82H; Fatigue; Digital image correlation; Local deformation; Welding
Effect of water vapor on tritium permeation behavior in the blanket system
Keywords: Solid breeder blanket; Water coexistence; Permeation; F82H; Pd–Ag
Diffusion bonding beryllium to Reduced Activation Ferritic Martensitic steel: Development of processes and techniques
Keywords: Beryllium; F82H; Diffusion; Bonding; HIP; Intermetallic
Overview of the TBM R&D activities in Japan
Keywords: Water cooled ceramic breeder TBM; Blanket module fabrication technology; F82H; High temperature Li–Pb blanket; Li/V blanket; Flibe blanket
Development of water-cooled solid breeder test blanket module in JAEA
Keywords: Blanket; Solid breeder; Water-cooled blanket; HIP; Test blanket module; Reduced activation ferritic steel; F82H; ITER; High-heat flux test; DATS
Status of engineering design of liquid lithium target in IFMIF-EVEDA
Keywords: IFMIF; Neutron source; Liquid lithium; Target; F82H; EUROFER; Remote handling; Radiation damage; DBTT; Design
Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules
Keywords: RAFM; F82H; TBM; WCSB; Fabrication; Weld; HAZ; Over-tempered HAZ; Irradiation effect
In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4
Keywords: Ceramic coating; Chemical densified coating method; Tritium permeation; Permeation reduction factor; In-pile experiment; F82H
Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3–SiO2 including CrPO4 (out-of-pile tests)
Keywords: Hydrogen; Deuterium; Permeability; Permeation reduction factor; F82H; Ceramic coating
First wall and divertor engineering research for power plant in JAERI
Keywords: Fusion power plant; PFC; F82H; Screw tube; HIP bonding; Thermal fatigue
Critical heat flux testing on screw cooling tube made of RAFM-steel F82H for divertor application
Keywords: Screw tube; RAFM; F82H; Divertor; High heat flux components; PFC; Water-cooled fusion DEMO reactor;