Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Thermal hydraulics; Flow characterization; Hexagonal fuel bundle; Comparison of experimental and simulation results;
مقالات ISI راکتور سریع سدیم را خنک می کند (ترجمه نشده)
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Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Wire-wrap pin bundle; Sub-channel flow; Inserts; CFD; Experiments; PEC;
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Wire wrapped assembly; Subchannel analysis; Pressure drop correlations; Flow mixing correlations;
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; SIMMER-III code; Power excursion simulation; Fuel-steel mixing effect; Mesh size effect;
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Annular linear induction pump; Equivalent circuit; Sodium test results;
Weighted-SMOTE: A modification to SMOTE for event classification in sodium cooled fast reactors
Keywords: راکتور سریع سدیم را خنک می کند; Imbalanced data set; Over-sampling; SMOTE; Sodium cooled fast reactor;
Heat transfer performance test of PDHRS heat exchangers of PGSFR using STELLA-1 facility
Keywords: راکتور سریع سدیم را خنک می کند; Decay heat removal system; Sodium heat exchanger; Sodium thermal-hydraulic test facility; Sodium cooled fast reactor;
Analysis of composition and temperature of debris bed based on settling characteristics of relocated core debris in pool type SFR
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled Fast Reactor; Core meltdown accident; Debris bed; Post Accident Heat Removal; Terminal settling velocity; Differential settling;
Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Depletion calculations; KANEXT; SERPENT
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Keywords: راکتور سریع سدیم را خنک می کند; Inherent Safety; Metal Fuel; Passive Safety; Pool Type; Sodium Cooled Fast Reactor;
SAS4A analysis on hypothetical total instantaneous flow blockage in SFRs based on in-pile experiments
Keywords: راکتور سریع سدیم را خنک می کند; SFR; Sodium cooled fast reactor; Monju; Safety; Severe accident; LF;
Estimation of radionuclide transport to reactor containment building under unprotected severe accident scenario in SFR
Keywords: راکتور سریع سدیم را خنک می کند; Radionuclide transport; Fission product inventory; Sodium cooled fast reactor; Hypothetical core disruptive accident; Reactor containment building
Simulation of some performance-related events of KALIMER-600
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; KALIMER-600; Performance-related event;
Application of RCC-MR for the structural design of tube sheet of intermediate heat exchanger for a sodium cooled fast reactor
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Isotropic equivalent solid plate; Finite element analysis; Linearization; Rim junction; RCC-MR code; Creep–fatigue damage at interface of solid and perforated portion; Groove effect on interface
Considerations on the potential use of Nuclear Small Modular Reactor (SMR) technology for merchant marine propulsion
Keywords: راکتور سریع سدیم را خنک می کند; ABWR; Advanced Boiling Water Reactor; AECL; Atomic Energy of Canada Ltd.; BWR; Boiling Water Reactor; CRP; Contra Rotating Propeller; C4TX; Centre for Tankship eXcellence; DCNS; Direction Technique des Constructions Navales of France; EFPY; Effective Full
Neutronic analysis of SFR core with HELIOS-2, Serpent, and DYN3D codes
Keywords: راکتور سریع سدیم را خنک می کند; HELIOS-2; Serpent; Monte Carlo; DYN3D; Few-group cross section generation; Sodium cooled fast reactor;
Theoretical and numerical studies of TWR based on ESFR core design
Keywords: راکتور سریع سدیم را خنک می کند; Traveling wave reactor (TWR); Sodium cooled fast reactor; Burn-up; Radial fuel shuffling
Application of the modified neutron source multiplication method to the prototype FBR Monju
Keywords: راکتور سریع سدیم را خنک می کند; Monju; ERANOS; Sodium cooled fast reactor; Mode extraction; Reactivity of sub-critical systems; Modified neutron source method
Prevention and mitigation of severe accident developments and recriticalities in advanced fast reactor systems
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Core disruptive accident (CDA); Recriticality; Controlled material removal (CMR); Total instantaneous blockage (TIB)
A fundamental approach to specify thermal and pressure loadings on containment buildings of sodium cooled fast reactors during a core disruptive accident
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Core disruptive accident; Containment building; Scaling laws; In-vessel sodium fire potential
Nuclear mechanism for TRU burning oxide fueled core in Advanced Recycling Reactor
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Transuranics; Sodium void reactivity; TRU transmutation; Advanced Recycling Reactor; GNEP
Experimental investigation on transfer characteristics of temperature fluctuation from liquid sodium to wall in parallel triple-jet
Keywords: راکتور سریع سدیم را خنک می کند; Sodium cooled fast reactor; Temperature fluctuation; Thermal striping; Heat transfer; Transfer function