Keywords: راکتور سریع; Sodium void reactivity; Fast reactor; Sodium-plenum; Void propagation;
مقالات ISI راکتور سریع (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 سریع; Fast reactor; Mixed-oxide fuel element; Cesium; Cesium molybdate; Cesium uranates; Fuel cladding mechanical interaction;
Keywords: راکتور سریع; Fast reactor; A three-loop diagram; High temperature; Sodium; Impurities; Hydrogen; Tritium; Corrosion products; Purification system; Security; Steel;
Keywords: راکتور سریع; Corium; Fast reactor; Uranium dioxide;
Keywords: راکتور سریع; Cross section adjustment; Systematic error; Stochastic error; Fast reactor;
Keywords: راکتور سریع; Steam generator tube rupture; Fast reactor; HXTR; HLM cooled reactor; Nuclear safety; Sustainable energy;
Keywords: راکتور سریع; Fast reactor; Convex shaped core; Thermal-hydraulic feasibility; Recriticality;
Keywords: راکتور سریع; fast reactor; fusion reactor; accelerator driven system; liquid metal; air ingress accident;
Keywords: راکتور سریع; Minor actinide; Uncertainty; Transmutation; Fast reactor; Plutonium production;
Keywords: راکتور سریع; Fluoride salts; Coolant selection; Neutron balance; Thorium cycle; Fast reactor;
Keywords: راکتور سریع; KUCA; Fast reactor; LEU; Feasibility; Reactor characteristics;
Keywords: راکتور سریع; Core disruptive accident; Post accident decay heat removal; Natural convection; Fast reactor; Core catcher;
Keywords: راکتور سریع; Fast reactor; Fuel pin bundle; Spacer wire; Bundle-duct interaction; Pin bowing; Void swelling; Irradiation creep; Thermal hydraulics; Subchannel;
Keywords: راکتور سریع; Nuclear energy; Fast reactor; Breeder; Neutronic performance; Fuel cycle; Metal fuel; Technology development; Sodium facilities; Safety studies; Material development; FBR; Fast Breeder Reactor; FBTR; Fast Breeder Test Reactor; PFBR; Prototype Fast Breeder
Keywords: راکتور سریع; Fast reactor; BN; PHENIX; Emergency heat removal system; Inherent safety; Decay heat removal; Natural circulation; Pump;
Keywords: راکتور سریع; Fast reactor; High-temperature, Sodium; Hydrogen production; Pool-type configuration; Neutronics; Thermal physics; Safety issues; Steels;
Keywords: راکتور سریع; Fast reactor; Thorium; Radiotoxicity; Fuel cycle; Decay heat; Transmutation;
Keywords: راکتور سریع; Fast Reactor; hydrodynamic process; mesh-characteristic method; sodium-water reaction; steam generator;
Keywords: راکتور سریع; Neutron spectrometer; Fast reactor; Diamond detector;
Keywords: راکتور سریع; CFD; Small modular reactor; Fast reactor; LFR; Natural circulation characteristics;
Keywords: راکتور سریع; Nuclear fission wave; Traveling wave reactor; Fast reactor; CANDLE; Stability; Reactivity feedback;
Keywords: راکتور سریع; Supercritical-pressure light water-cooled reactor; Core design; Fast reactor;
Keywords: راکتور سریع; Small modular reactor; Fast reactor; Long burning cycle; Lead–bismuth eutectic; Natural circulation; Passive safety
Keywords: راکتور سریع; Fast reactor; Radiotoxicity; Transmutation; Fuel cycle; Decay heat; Spent nuclear fuel; CORAIL; LWR fuel assembly containing U-TRU fuel pins and LEU pins; EPR; European pressurized reactor; LEU; low enriched uranium; LWR; light water reactor; MA; minor ac
Keywords: راکتور سریع; Ultrasonic; Decontamination; Radio-active; MOX fuel pin; Fast reactor;
Keywords: راکتور سریع; Fast reactor; Delayed neutrons; Clad failure simulation; Sensitivity
Keywords: راکتور سریع; Small Modular Reactor; Lead cooled; Fast reactor; Natural circulation; Thermal-hydraulics;
Keywords: راکتور سریع; Molten salt reactor; Neutron Transport; Fast reactor; Nuclear power; Nuclear reactor; Neutron shielding
Keywords: راکتور سریع; Molten Salt; Fast Reactor; Thorium cycle; Neutronics; Reprocessing influence
Keywords: راکتور سریع; Fast reactor; Sodium flow; Pin bundle; Porous blockage; CFD
Keywords: راکتور سریع; Technology readiness level; Partitioning; Transmutation; Fast reactor; Accelerator driven system; Actinide fuel cycle
Keywords: راکتور سریع; Neutron noise; Fast reactor; Hexagonal geometry; ESFR;
Keywords: راکتور سریع; Fast Reactor; Thorium; Fuel cycle; Safety; Fuel handling;
Keywords: راکتور سریع; Fuel cycle; Simulation; Modeling; Code; Scenario; Thermal reactor; Fast reactor; Nuclide composition; Recycling; Plutonium equivalenting; Store; Minor actinides
Keywords: راکتور سریع; Fast reactor; Flow-induced vibration; Swirling flow; Flow separation
Keywords: راکتور سریع; Minor actinide; Transmutation; Fast reactor; Fission; Plutonium production
Keywords: راکتور سریع; Fast reactor; Sodium; Clad failure; Fission products; Neutron detection; Photoneutron noise
Keywords: راکتور سریع; Fast reactor; MOX fuel; Nitride fuel; Sodium void reactivity effect; Maximal burnup; Transient; Safety
Keywords: راکتور سریع; Fast reactor; Swelling; Irradiation creep; Guide tubes; Safety rods; Temperature gradients; Damage dose gradients; Ovality
Keywords: راکتور سریع; Severe beyond design-basis accident; KUPOL-BN code; NOSTRADAMUS code; SOKRAT-BN integrated code; Fast reactor; Fission products; Substantiation of BN reactor safety
Keywords: راکتور سریع; International forum Gen-IV; Fast reactor; Sodium; Lead; Supercritical water; MOX fuel; Closed fuel cycle; Spent nuclear fuel; Transmutation of minor actinides
Optimization design research for 89Sr production in China Experimental Fast Reactor
Keywords: راکتور سریع; Fast reactor; Irradiation; 89Sr;
Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code
Keywords: راکتور سریع; Thorium; Fast reactor; GCFR; Pu; Minor actinides; MCNPX;
FASt TEst Reactor (FASTER) design overview
Keywords: راکتور سریع; Fast reactor; Test reactor; Reactor design; Advanced reactor;
Core design and performance of the FASt TEst reactor (FASTER)
Keywords: راکتور سریع; Fast reactor; Test reactor; Neutronics; Reactor physics; Irradiation performance; Core design;
Thermo-mechanical behaviour of primary system components of future FBR during crash Cooling: A numerical simulation
Keywords: راکتور سریع; Fast reactor; Crash cooling; Creep-fatigue damage; Thermomechanical analysis; Thermal shock;
SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification
Keywords: راکتور سریع; Fast reactor; Neutronics; Verification; Validation; Uncertainty quantification;
The effect of homogenization on the neutronic parameters and transmutation of GFR-2400 fast reactor fuel assembly
Keywords: راکتور سریع; Fast reactor; GFR2400; MCNPX; Homogenization; Transmutation;
Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems
Keywords: راکتور سریع; Fast reactor; Thermal-hydraulics; Point-kinetics; Transient; Passive safety; ULOF;
A refined analysis on the power reactivity loss measurement in Monju
Keywords: راکتور سریع; Power reactivity loss; JENDL-4.0; Monju; Fast reactor;