Keywords: پتو; Hydrogen; Tritium; Reduced activation ferritic/martensitic steel; Permeation; Blanket;
مقالات ISI پتو (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
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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: پتو; Fusion; Nuclear; Plasma; Blanket; Divertor; Systems;
Keywords: پتو; FFHR; Ferromagnetism; Blanket; Magnetic field distortion;
Keywords: پتو; Blanket; Helium pressure drop; Porous media; Randomly packed spheres;
Keywords: پتو; Fusion; Energy; Blanket; Beryllium; Neutronics;
Keywords: پتو; Fusion; Tritium; TBR; Neutronics; Parameter; Blanket;
Keywords: پتو; Blanket; Nuclear-thermal coupling; Radial build optimization;
Keywords: پتو; Operant conditioning; Blanket; Rug; Thermoregulation; Cognition; Clicker training;
Keywords: پتو; Fusion reactor; Thermonuclear; Deuterium; Tritium; Economics; Magnet; Neutronics; Reliability; Availability; Capacity factor; Blanket; Divertor; DEMO;
Keywords: پتو; Fusion; CFETR; Blanket; Structure; Thermo-mechanical analysis
Keywords: پتو; Fusion; Engineering testing reactor; Lead–lithium; Blanket
Keywords: پتو; Screen printing; Ink transfer; Blanket; Silicone resin; Conductive pattern
Keywords: پتو; HCPB; Blanket; DEMO
Keywords: پتو; air; anesthesia; blanket; dog; hypothermia; warm;
MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF
Keywords: پتو; Blanket; Lead-lithium; DCLL; FNSF; Magnetohydrodynamics; Pressure drop;
Numerical study of the MHD flow around a bounded heating cylinder: Heat transfer and pressure drops
Keywords: پتو; MHD; Pressure drop; Heat transfer coefficient; Flow around cylinder; Liquid metals; Blanket;
ITER blanket manifold final design and validation
Keywords: پتو; Blanket; Manifolds; Inboard; Outboard; Co-axial; Validation; Tolerances; Pipes; 316L;
Model-based optimization of the heat flux distribution of IR-heaters for high heat flux testing
Keywords: پتو; High heat flux; Plasma facing components; Blanket; First Wall; HELOKA;
Flow characteristics analysis of purge gas in unitary pebble beds by CFD simulation coupled with DEM geometry model for fusion blanket
Keywords: پتو; Blanket; Pebble bed; Purge gas; DEM-CFD; Flow characteristics;
Full Length ArticleNumerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR
Keywords: پتو; CFETR; Blanket; Coupling analysis; Neutronics; Thermal-hydraulics; Thermo-mechanics;
A new blanket tritium recovery experiment with intense DT neutron source at JAEA/FNS
Keywords: پتو; DT neutron; Tritium; Blanket; Ionization chamber; Tritium recovery; JAEA/FNS;
Comparison over the nuclear analysis of the HCLL blanket for the European DEMO
Keywords: پتو; DEMO; Neutronics; Blanket; HCLL; Tritium breeding; Nuclear heating; TRIPOLI-4®;
On the hydraulic behaviour of ITER Shield Blocks #14 and #08. Computational analysis and comparison with experimental tests
Keywords: پتو; Blanket; CFD analysis; Hydraulics;
Overview of progress on the European DEMO remote maintenance strategy
Keywords: پتو; DEMO; Remote; Maintenance; Progress; Blanket; Divertor;
Investigation of effective thermal conductivity for pebble beds by one-way coupled CFD-DEM method for CFETR WCCB
Keywords: پتو; Blanket; Pebble bed; CFD-DEM; Effective thermal conductivity
Recent technical progress on BA Program: DEMO activities and IFMIF/EVEDA
Keywords: پتو; Broader approach; IFERC; IFMIF; DEMO; Design; R&D; Accelerator; Blanket;
Lightweight superinsulating Resorcinol-Formaldehyde-APTES benzoxazine aerogel blankets for space applications
Keywords: پتو; Superinsulation; Blanket; Aerogel; Organic-inorganic hybrid; Benzoxazine; Space applications
Analysis of the steady state hydraulic behaviour of the ITER blanket cooling system
Keywords: پتو; ITER; Blanket; Hydraulics;
SIRHEX-A new experimental facility for high heat flux testing of plasma facing components
Keywords: پتو; High heat flux; Plasma facing components; Blanket; First Wall; HELOKA;
Thermal-mechanical analysis of the first wall for CFETR helium cooled solid breeder blanket
Keywords: پتو; CFETR; Blanket; First wall; Thermal-mechanical; Optimization;
Optimization of the first wall for the DEMO water cooled lithium lead blanket
Keywords: پتو; DEMO; Blanket; WCLL; Design; First Wall;
Theoretical modeling of the effective thermal conductivity of the binary pebble beds for the CFETR-WCCB blanket
Keywords: پتو; Blanket; Binary pebble beds; Theoretical modeling; Effective thermal conductivity
Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR
Keywords: پتو; CFETR; Blanket; Neutronics; Thermal-hydraulics; Stress analysis;
Progress in the design of Normal Heat Flux First Wall panels for ITER
Keywords: پتو; ITER; Blanket; First-wall technology; CAD; FEM;
Engineering challenges and development of the ITER Blanket System and Divertor
Keywords: پتو; Blanket; Divertor;
An approach to verification and validation of MHD codes for fusion applications
Keywords: پتو; Blanket; Liquid metal magnetohydrodynamics; Computer code;
Blanket/first wall challenges and required R&D on the pathway to DEMO
Keywords: پتو; Blanket; First wall; Fusion nuclear technology; Tritium self-sufficiency; MHD; Ceramic breeders; Liquid metals; DCLL; Materials; Fusion nuclear science facility; Heat transfer; Mass transfer; Fusion technology;
Radiation induced deuterium absorption for RB-SiC, HP-SiC, silicon and graphite loaded during electron irradiation
Keywords: پتو; Deuterium; Radiation; Absorption; Blanket; RB-SiC
Influence of surface condition on deuterium release from Li2TiO3 pebble
Keywords: پتو; Tritium breeding material; Lithium titanate; Deuterium ion irradiation; Blanket; Tritium inventory
Pre-conceptual design assessment of DEMO remote maintenance
Keywords: پتو; DEMO; PPP&T; Remote handling; Maintenance; Divertor; Blanket
Heat transfer study for ITER blanket shield block cooling design
Keywords: پتو; ITER; Blanket; Shield block; Heat transfer
Development of the water cooled lithium lead blanket for DEMO
Keywords: پتو; DEMO; Blanket; WCLL; Design
Ion beam analyses for Li2TiO3 blanket candidate material
Keywords: پتو; NRBS; NRA; Blanket; Composition ratio; Composition change;
Activation analysis and waste management for blanket materials of multi-functional experimental fusion–fission hybrid reactor (FDS-MFX)
Keywords: پتو; Fusion; Fission; Hybrid; Multi-functional experimental reactor; Blanket; Activation
Strategy for solving a coupled problem of the electromagnetic load analysis and design optimization for local conducting structures to support the ITER blanket development
Keywords: پتو; Tokamak; ITER; Blanket; Electromagnetic transients; Eddy currents; Electromagnetic loads
HELIAS 5-B magnet system structure and maintenance concept
Keywords: پتو; Stellarator; HELIAS; Magnet; Structure; Blanket; Maintenance;
Neutronics and pumping power analyses on the Tokamak reactor for the fusion-biomass hybrid concept
Keywords: پتو; Neutronics; Pressure drop; LiPb; Blanket; Divertor
Effect of a magnetic field on stability and transitions in liquid breeder flows in a blanket
Keywords: پتو; Blanket; MHD flow; Stability and transitions; Mixed convection
Octalithium plumbate as breeding blanket ceramic: Neutronic performances, synthesis and partial characterization
Keywords: پتو; Blanket; Octalithium plumbate; Synthesis; XRD; TBR; Neutronic response
A model for tritium transport in fusion reactor components: The FUS-TPC code
Keywords: پتو; Tritium; Permeation; DEMO; HCLL; Blanket; Lithium–lead