Keywords: راکتور فیوژن; System codes; Tokamak; Fusion reactor; Plasma model; Code coupling;
مقالات ISI راکتور فیوژن (ترجمه نشده)
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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: راکتور فیوژن; Hydrogen bubbles; Ion implantation; Transmission electron microscopy; Tungsten; Electro-chemical polishing; Fusion reactor;
Keywords: راکتور فیوژن; Design; Creativity; Science to engineering; Fusion reactor; Liquid Lithium Ceramic Breeder;
Keywords: راکتور فیوژن; Fusion reactor; DEMO; Uncertainty quantification; Systems studies;
Keywords: راکتور فیوژن; Tritium; TAS; Fuel cycle; Fusion reactor; System dynamics;
Keywords: راکتور فیوژن; fast reactor; fusion reactor; accelerator driven system; liquid metal; air ingress accident;
Behaviour of hydrogenated lead-lithium alloy
Keywords: راکتور فیوژن; Pb-Li eutectic alloy; Hydrogen solubility; Fusion reactor; Liquid breeders; Tritium;
Keywords: راکتور فیوژن; Spherical tokamak; Fusion reactor; Modular approach;
Keywords: راکتور فیوژن; Tritium; Dust; Dose; Fusion reactor; Environment restoration;
Keywords: راکتور فیوژن; Fusion reactor; Liquid blanket; Tritium; Lithium isotope abundance;
Keywords: راکتور فیوژن; Fusion reactor; Thermonuclear; Deuterium; Tritium; Economics; Magnet; Neutronics; Reliability; Availability; Capacity factor; Blanket; Divertor; DEMO;
Keywords: راکتور فیوژن; Fusion reactor; Neutron measurements; Absolute calibration; Fusion power
Keywords: راکتور فیوژن; Radio frequency ion sources; Neutral beam injection system; Fusion reactor; Self-excited oscillator; Solid state generator
Keywords: راکتور فیوژن; SES; Fusion reactor; Divertor; Tile; Thimble; Heat transfer enhancement
Keywords: راکتور فیوژن; Metal oxide coating; Fusion reactor; Carbon contamination; Reflectivity;
Keywords: راکتور فیوژن; Fusion reactor; Thermonuclear; Deuterium; Tritium; Economics
CFETR integration design platform: Development of space analysis module
Keywords: راکتور فیوژن; Integrated design; Space analysis; Deformation; Fusion reactor; CFETR;
Impact of thermal fatigue on W-W brazed joints for divertor components
Keywords: راکتور فیوژن; Tungsten; Brazing; Fusion reactor; High heat flux; Plasma facing component; Thermal fatigue;
Interfacial characterization by TEM and nanoindentation of W-Eurofer brazed joints for the first wall component of the DEMO fusion reactor
Keywords: راکتور فیوژن; Eurofer97; Tungsten; Fusion reactor; Interfacial characterization; Plasma facing component;
Validation of COMSOL code for analyzing liquid metal magnetohydrodynamic flow
Keywords: راکتور فیوژن; Fusion reactor; Hartmann number; Interaction parameter; Liquid breeder blanket; Magnetohydrodynamics; Wall conductance ratio;
Investigations of the mechanical properties and structure of laser welds for ITER divertor and first wall
Keywords: راکتور فیوژن; Laser welding; Mechanical properties; Hardness; Fusion reactor;
High heat flux performance of W-Eurofer brazed joints
Keywords: راکتور فیوژن; Tungsten; Eurofer; Brazing; Fusion reactor; High heat flux; Plasma facing component;
Investigation of (n, p), (n, 2n) reaction cross sections for Sn isotopes for fusion reactor applications
Keywords: راکتور فیوژن; Sn isotopes; Fusion reactor; Thermonuclear reactor; TALYS-1.8; EMPIRE-3.2.2;
Comparative studies of H absorption/desorption kinetics and evaporation of liquid lithium in different porous systems and free surfaces
Keywords: راکتور فیوژن; Lithium; Liquid metals; Fusion reactor; Tritium retention; CPS systems;
Structural analysis for the joint of the ITER ELM coil
Keywords: راکتور فیوژن; Joint; ELM coil; Fusion reactor; Structural analysis;
A novel low-temperature approach for fabricating α-Al2O3-based ceramic coating as tritium permeation barrier
Keywords: راکتور فیوژن; Al2O3; Coating; Low-temperature fabrication; Fusion reactor; Tritium permeation barrier;
Control strategy for mitigation of pulsed heat load transferred to ITER cryoplant from magnets
Keywords: راکتور فیوژن; Fusion reactor; Cryogenic circuit; Cryoplant; Heat load mitigation; Thermal-hydraulic analysis; Control algorithm;
Systems code studies on the optimization of design parameters for a pulsed DEMO tokamak reactor
Keywords: راکتور فیوژن; Tokamak; Fusion reactor; Systems code;
Development of technology for fabrication of lithium CPS on basis of CNT-reinforced carboxylic fabric
Keywords: راکتور فیوژن; Divertor; Fusion reactor; Lithium capillary-porous system (CPS); Carbon nanotubes (CNT); Carboxylic fabric; Lithium;
Evaluation of mechanically alloyed Cu-based powders as filler alloy for brazing tungsten to a reduced activation ferritic-martensitic steel
Keywords: راکتور فیوژن; Tungsten; Eurofer; Brazing; Fusion reactor; Joining; Plasma facing component;
Conceptual design of a liquid metal limiter/divertor system for the FFHR-d1
Keywords: راکتور فیوژن; Liquid metal; Divertor; High heat load; Particle control; Vacuum pumping; Fusion reactor; Heliotron;
Divertor power spreading in DEMO reactor by impurity seeding
Keywords: راکتور فیوژن; Numerical modeling; Edge plasma; Impurity seeding; Fusion reactor;
Study of a novel brazing process for W-W joints in fusion applications
Keywords: راکتور فیوژن; Tungsten; Brazing; Fusion reactor; Joining; Plasma facing component;
Dynamic evaluation of environmental impact due to tritium accidental release from the fusion reactor
Keywords: راکتور فیوژن; Fusion reactor; Accidental release; Public dose; Tritium release amount
Impurity radiation in DEMO systems modelling
Keywords: راکتور فیوژن; Fusion reactor; DEMO; Systems studies; Radiation
A new meshless approach to map electromagnetic loads for FEM analysis on DEMO TF coil system
Keywords: راکتور فیوژن; Fusion reactor; Magnetic loads; Mapping; FEA; Radial basis functions; DEMO; TF coil;
Laboratory studies of H retention and LiH formation in liquid lithium
Keywords: راکتور فیوژن; Lithium; Liquid metals; Fusion reactor; Tritium retention; Isotope exchange
Assessment of radioactive wastes from a DCLL fusion reactor: Disposal in El Cabril facility
Keywords: راکتور فیوژن; Fusion reactor; DCLL blanket; Clearance; Waste disposal; El Cabril
Research and development status on fusion DEMO reactor design under the Broader Approach
Keywords: راکتور فیوژن; DEMO; Fusion reactor; Divertor; Remote maintenance; Safety
Solid solubility of hydrogen in Pb83Li17 alloy: A preliminary investigation
Keywords: راکتور فیوژن; Hydrogen solid solubility; Pb83Li17 alloy; Fusion reactor; Enthalpy; Entropy
Conceptual design of a water cooled breeder blanket for CFETR
Keywords: راکتور فیوژن; Fusion reactor; Solid blanket; Water coolant; Superheated steam; Tritium breeding ratio
First tests of the ion irradiation and implantation beamline at the CMAM
Keywords: راکتور فیوژن; Ion implantation; Beam sweep system; Cryostat furnace; Fusion reactor; Quartz waveguide;
Mechanical properties and microstructural investigations of TIG welded 40 mm and 60 mm thick SS 316L samples for fusion reactor vacuum vessel applications
Keywords: راکتور فیوژن; Fusion reactor; TIG welding; Non-destructive tests; Mechanical properties; Microstructure; Delta ferrite
Numerical studies on helium cooled divertor finger mock up with sectorial extended surfaces
Keywords: راکتور فیوژن; Jet-impingement; CFD; Sectorial extended surfaces; Tile; Thimble; Fusion reactor
Prospects for the use of high-Tc superconductors in fusion magnets and options for their test in SULTAN
Keywords: راکتور فیوژن; Coated conductor; Fusion reactor; HTS conductor test; Magnet system; RE-123; SULTAN;
Numerical simulation of a blanket cooling system for fusion reactor based on PWR conditions
Keywords: راکتور فیوژن; Numerical simulation; Water-cooled blanket; PWR; Fusion reactor; CFD
Development of technology for recovering lithium from seawater by electrodialysis using ionic liquid membrane
Keywords: راکتور فیوژن; Tritium breeder; Lithium resource; Fusion reactor; Seawater; Ionic liquid
Studies on the solubility of hydrogen in molten Pb83Li17 eutectic alloy
Keywords: راکتور فیوژن; Pb83Li17 eutectic alloy; Hydrogen solubility; Fusion reactor; Tritium; ITER
Development of ITER tritium transport package
Keywords: راکتور فیوژن; Tritium; Transport package; Safety analysis; Fusion reactor
Conceptual study of vertical sector transport maintenance for DEMO fusion reactor
Keywords: راکتور فیوژن; Maintenance; Vertical sector transport; DEMO; Design; Fusion reactor