Keywords: راکتور سریع سدیم خنک; Reactor vessel cooling system; Code development; Sodium-cooled fast reactor; Sensitivity analysis;
مقالات ISI راکتور سریع سدیم خنک (ترجمه نشده)
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Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Debris bed formation; Flow regime; Bottom-heated boiling;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Molten pool; Sloshing behavior; Experimental study;
Keywords: راکتور سریع سدیم خنک; Liquid sloshing; Sodium-cooled fast reactor; Shaking table experiment; VOF;
Keywords: راکتور سریع سدیم خنک; Liquid jet impingement; Splashing rate; Droplet size; Jet breakup; Impact frequency; Sodium-cooled fast reactor;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Molten pool; Fuel-coolant interaction; Pressure characteristics;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Metallic fuel; Specified acceptable fuel design limits; Pin-level analysis;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Pool sloshing behavior; Solid particles; Flow regime;
Keywords: راکتور سریع سدیم خنک; BFC; Bottom of Fissile Column; CESAR; Circuit d'Etude de l'ébullition du Sodium lors d'un Accident de Réactivité; OCARINa; Outil de Calcul Analytique Rapide pour les Insertions de réactivité dans un réacteur à neutrons rapides refroidis au so
Keywords: راکتور سریع سدیم خنک; Inter-wrapper flow; Sodium-cooled fast reactor; Code development; Sensitivity analyses;
Keywords: راکتور سریع سدیم خنک; Fuel cycle analysis; Thorium fuel; Breed-and-Burn concept; Sodium-cooled fast reactor;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Debris bed formation; Flow regime; Gas injection;
Keywords: راکتور سریع سدیم خنک; Core Disruptive Accident; Debris Bed Formation; Flow Regime; Nonspherical Particles; Sodium-cooled Fast Reactor;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Sodium; Water; Elemental reactional; Laser diagnostics;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Nuclear fuel slugs; Injection casting; Rare earth elements; Uranium-zirconium alloys;
Keywords: راکتور سریع سدیم خنک; CFD; Sodium-cooled fast reactor; Porous media approach; Intermediate Heat Exchanger;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Debris bed formation; Experimental study; Regime map;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Debris bed formation; Experimental study;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Melt coolant interactions; Jet breakup; Droplet formation; Liquid-liquid systems; Breakup regime;
Keywords: راکتور سریع سدیم خنک; Ultra-long-life core; Sodium-cooled fast reactor; Self-controllability
Keywords: راکتور سریع سدیم خنک; Moderated minor actinide target; Two-stage fuel cycle option; Sodium-cooled fast reactor; Accelerator driven system;
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Severe accident; Local fuel-coolant interaction; Molten pool; Pressure-buildup; Mechanical energy;
Keywords: راکتور سریع سدیم خنک; Severe accident; Fission product; Thermochemistry; Chemical form; Sodium-cooled fast reactor
Keywords: راکتور سریع سدیم خنک; Decay heat removal system; In-service inspection; Intermediate sodium system; Materials; Safety criteria; Sodium-cooled fast reactor; Sodium-heated steam generator
Keywords: راکتور سریع سدیم خنک; Cooling time; Pyroprocessing; Recovery factor; Recycle scenario; Sodium-cooled fast reactor; Spent fuel
Keywords: راکتور سریع سدیم خنک; B&BR; Sodium-cooled fast reactor; Lead-based reflector; LBE; LME; PbO;
Keywords: راکتور سریع سدیم خنک; 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 سدیم خنک; Sodium-cooled fast reactor; Core disruptive accident; Self-leveling; Debris bed; Empirical approach; Model validation;
Keywords: راکتور سریع سدیم خنک; Sodium-Cooled Fast Reactor; Closed fuel cycle; Minor actinide management; Improved safety performance; Long term development experience; Generation IV International Forum;
Estimation of porosity and void fraction profiles in a packed bed of spheres using X-ray radiography
Keywords: راکتور سریع سدیم خنک; Two-phase flow; Sodium-cooled fast reactor; Packed bed of spheres; Porosity; Void fraction;
Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Wire wrapped spacer; U-pattern; CFD; Sub-channel;
Model calculation of Cr dissolution behavior of ODS ferritic steel in high-temperature flowing sodium environment
Keywords: راکتور سریع سدیم خنک; Oxide dispersion strengthened steel; Fuel cladding tube; Sodium-cooled fast reactor; Cr dissolution; Flowing sodium;
A lumped parameter modelling of particle generation from Na-pool fires in SFR containments
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; In-containment source term; Sodium-pool fire; Particle generation model; Correlations;
Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system
Keywords: راکتور سریع سدیم خنک; Transient analysis; Sodium-cooled fast reactor; ULOF; UTOP; UCRW;
Safety analysis of the FASt TEst reactor (FASTER) preconceptual design
Keywords: راکتور سریع سدیم خنک; FASTER; Sodium-cooled fast reactor; SAS4A/SASSYS-1; Safety;
Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Subchannel analysis code; Thermal-hydraulic performance;
Core geometry for recriticality prevention against CDA in sodium-cooled fast reactor
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; CDA; Recriticality prevention; Core geometry; Reactor physics;
Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor
Keywords: راکتور سریع سدیم خنک; Control Rod Assembly; Drop Time; Drop Velocity; Free Drop; Seismic Loading; Sodium-cooled Fast Reactor;
Effects of long-time service at high temperature on the material strength and J-R curve of Grade 91 steel
Keywords: راکتور سریع سدیم خنک; ASME-NH; ASME Section III Division 1 Subsection NH; CCG; creep crack growth; DHX; decay heat exchanger; ETD; elevated temperature design; FHX; forced-draft sodium-to-air heat exchanger; Gen IV; generation IV; Gr.91; Grade 91; J-R; J-integral Resistance; L
Investigation of CO2 leak accident in SFR coupled with S-CO2 Brayton cycle
Keywords: راکتور سریع سدیم خنک; Sodium-cooled Fast Reactor; Supercritical CO2 power cycle; Na-CO2 reaction; Supercritical CO2 critical flow; Na2CO3 cleaning agent;
Thermodynamic analysis and preliminary design of closed Brayton cycle using nitrogen as working fluid and coupled to small modular Sodium-cooled fast reactor (SM-SFR)
Keywords: راکتور سریع سدیم خنک; Sodium-cooled fast reactor; Closed Brayton cycle; Nitrogen working fluid; Thermodynamic analysis; Heat exchanger design; Turbomachinery design;
Thermal–hydraulic design and analysis code development for steam generator of CFR600
Keywords: راکتور سریع سدیم خنک; Sodium-cooled Fast Reactor; China Fast Reactor 600; Steam generator design; Thermal–hydraulic model; Sensitivity analysis
A comparison between oxide and metallic fueled ASTRID-like reactors
Keywords: راکتور سریع سدیم خنک; ASTRID; Sodium-cooled fast reactor; Oxide fuel; Metallic fuel;
Validation of the finned sodium-air heat exchanger model in MARS-LMR
Keywords: راکتور سریع سدیم خنک; MARS-LMR; Finned sodium-air heat exchanger; Sodium-cooled fast reactor; PFBR; JOYO;
Comparative assessment of CANDU 6 and Sodium-cooled Fast Reactors for nuclear desalination
Keywords: راکتور سریع سدیم خنک; Desalination; Nuclear plant; CANDU; Sodium-cooled Fast Reactor; Energy; Exergy; Efficiency;
Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor
Keywords: راکتور سریع سدیم خنک; Ferritic-Martensitic Steel; Irradiation Test; Metal Fuel; Pyroelectrochemical; Sodium-cooled Fast Reactor; Spent Fuel; Transuranic Fuel;
Assessment calculation of MARS-LMR using EBR-II SHRT-45R
Keywords: راکتور سریع سدیم خنک; SFR; sodium-cooled fast reactor; EBR-II; Experimental Breeder Reactor-II; SHRT; Shut-down Heat Removal Test; ANL; Argonne National Laboratory; IHX; intermediate heat exchanger; GP; grid plate; ACLP; above core load pad; CRDL; control rod drive-line; RV; r
Microstructural evolution in NF616 (P92) and Fe-9Cr-0.1C-model alloy under heavy ion irradiation
Keywords: راکتور سریع سدیم خنک; Generation-IV nuclear reactors; Sodium-cooled fast reactor; Heavy ion irradiation; In situ technique; Transmission electron microscopy; Ferritic-martensitic alloys; Model alloys;
Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR code
Keywords: راکتور سریع سدیم خنک; Sodium-cooled Fast Reactor; Pool-type; Asymmetry test; Multi-dimensional modeling; MARS-LMR code;
Mapping of the thermodynamic performance of the supercritical CO2 cycle and optimisation for a small modular reactor and a sodium-cooled fast reactor
Keywords: راکتور سریع سدیم خنک; Supercritical CO2 cycle; Condensing mode; Efficiency; Irreversibility; Small modular reactor; Sodium-cooled fast reactor