A refined analysis on the power reactivity loss measurement in Monju
Keywords: راکتور سریع; Power reactivity loss; JENDL-4.0; Monju; Fast reactor;
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Microwave based oxidation process for recycling the off-specification (U,Pu)O2 fuel pellets
Keywords: راکتور سریع; Fast reactor; MOX fuel; Recycling; Oxidation; Microwave;
Integrated CFD investigation of heat transfer enhancement using multi-tray core catcher in SFR
Keywords: راکتور سریع; Severe accident; Core catcher; Fast reactor; PAHR; Natural convection;
Optimization of the heterogeneous GFR 2400 control rod design
Keywords: راکتور سریع; Gas-cooled Fast Reactor; GFR 2400; Reactivity control system; Moderator utilization; Fast reactor; Heterogeneous control rod design;
Thermal hydraulic analysis of a passively controlled DHR system
Keywords: راکتور سریع; Passive safety system control; ALFRED; Fast reactor; Relap5; Thermalhydraulics; Liquid metals;
Stationary liquid fuel fast reactor SLFFR - Part I: Core design
Keywords: راکتور سریع; Fast reactor; TRU burning; Zero conversion ratio; Liquid metal fuel;
Stationary liquid fuel fast reactor SLFFR - Part II: Safety analysis
Keywords: راکتور سریع; Passive safety; Fast reactor; Liquid fuel reactor; Unprotected accidents;
Silicon-containing ferritic/martensitic steel after exposure to oxygen-containing flowing lead-bismuth eutectic at 450 and 550 °C
Keywords: راکتور سریع; Fast reactor; Accelerator driven system; Liquid metal corrosion; Oxidation;
Conjugate heat transfer investigation of core damage propagation during total instantaneous blockage in SFR fuel subassembly
Keywords: راکتور سریع; Total instantaneous blockage; Fuel subassembly; Fast reactor; Damage propagation; Natural convection
Molten salt fast reactor with U–Pu fuel cycle
Keywords: راکتور سریع; Liquid nuclear fuel; Fast reactor; Molten salt reactor; Solubility of the minor actinides; Subcritical reactor-burner
SFR with once-through depleted uranium breed & burn blanket
Keywords: راکتور سریع; Fast reactor; Seed and blanket; Breed and burn; Depleted uranium; S-PRISM
Oxidation and carburizing of FBR structural materials in carbon dioxide
Keywords: راکتور سریع; Fast reactor; Supercritical carbon dioxide; Corrosion; Structural materials; CO2 turbine cycle
Comparison of transient analysis of LBE-cooled fast reactor and ADS under loss of heat sink accident
Keywords: راکتور سریع; Safety analysis; NTC; Fast reactor; ADS; Loss of heat sink;
An investigation on Unprotected Loss of Flow Accident in Th–Pu metal fuelled 500 MWe fast reactor
Keywords: راکتور سریع; Fast reactor; Advanced fuels; Transient analysis; ULOFA; Sodium voiding; PREDIS
Basic verification of THACS for sodium-cooled fast reactor system analysis
Keywords: راکتور سریع; Fast reactor; Benchmark analysis; Code verification
Design and performance of 2D and 3D-shuffled breed-and-burn cores
Keywords: راکتور سریع; Breed and burn; Traveling Wave; Core design; Fast reactor; Shuffling; LMFBR;
Accuracy of nuclear design of fast and thermal neutron coupled core by SRAC
Keywords: راکتور سریع; Supercritical-pressure; Light water cooling; Fast reactor; MVP; SRAC; Zirconium hydride
Application of safety analysis code SIMMER-IV to blockage accidents in FASTEF subcritical core
Keywords: راکتور سریع; Fast reactor; Lead–Bismuth Eutectic; Safety analysis; Unprotected blockage
A CFD based approach for thermal hydraulic design of main vessel cooling system of pool type fast reactors
Keywords: راکتور سریع; Fast reactor; Main vessel; Computational fluid dynamics; Heat load; Shell ovality; Jet breakers;
A robust thermal model to investigate radial propagation of core damage due to total instantaneous blockage in SFR fuel subassembly
Keywords: راکتور سریع; Total instantaneous blockage; Fuel subassembly; Fast reactor; Damage propagation; Voller's algorithm;
Criticality safety studies for plutonium–uranium metal fuel pin fabrication facility
Keywords: راکتور سریع; Fast reactor; Metal fuel; Criticality; Fuel fabrication; Sodium bonding; Monte Carlo
Safety analysis of a supercritical water cooled fast reactor with all-upward two-pass flow
Keywords: راکتور سریع; Supercritical water; Fast reactor; Safety analysis; Upward flow
A SCENARIO STUDY ON MIXING STRATEGIES OF FAST REACTOR WITH LOW AND HIGH CONVERSION RATIOS
Keywords: راکتور سریع; Conversion Ratio; Fast Reactor; Spent Fuel; Transuranic Element; Fuel Cycle; Long-term Heat Load
Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR)
Keywords: راکتور سریع; Direct contact; Fast reactor; Lead-bismuth eutectic; Natural circulation; Safety
Hydraulic design of primary sodium header of a fast spectrum reactor by computational and experimental studies
Keywords: راکتور سریع; Fast reactor; Computational fluid dynamics; Air experiments; Minimization of pressure loss; Flow mal-distribution; Swirl
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure
Keywords: راکتور سریع; BEC; Beginning of Equilibrium Cycle; BOC; Beginning Of Cycle; BOL; Beginning Of Life; BR; Breeding Ratio; EEC; End of Equilibrium Cycle; EFPY; Equivalent Full Power Years; ELSY; European Lead SYstem; EOC; End Of Cycle; FA; Fuel Assembly; FP; Fission Produ
Feasibility of lead cooled breed and burn reactors
Keywords: راکتور سریع; Fast reactor; High burnup; Breed and burn; Modified open cycle; Uranium utilization; Advanced reactor
Design study on power flattening to sodium cooled large-scale CANDLE burning core with using thorium fuel
Keywords: راکتور سریع; CANDLE; Sodium; Fast reactor; Large-scale
Neutronic characterization and decay heat calculations in the in-vessel fuel storage facilities for MYRRHA/FASTEF
Keywords: راکتور سریع; Fast reactor; Neutronic design; Decay heat
Sensor development for position detection of diverse safety rod of fast reactor
Keywords: راکتور سریع; Fast reactor; DSR free fall time; Eddy current sensor; Inductive coupling;
Power control of CANDLE reactor by coolant flow rate
Keywords: راکتور سریع; CANDLE burn-up; Fast reactor; Reactivity feedback; Power control
Design Study on Pb-208 Cooled CANDLE Burning Reactors toward Practical Application for Future Nuclear Energy Source
Keywords: راکتور سریع; CANDLE burn-up; Fast reactor; Lead-208; Metallic fuel
Effect of minor actinides doping on plutonium produced in large-scale FBR blanket
Keywords: راکتور سریع; Proliferation resistance; Plutonium; Minor actinides; Fast reactor; Blanket
Corrosion resistance of ceramics SiC and Si3N4 in flowing lead-bismuth eutectic
Keywords: راکتور سریع; Ceramics; SiC; Lead-bismuth; Corrosion; Fast reactor; Accelerator driven system
Remote field eddy current testing for steam generator inspection of fast reactor
Keywords: راکتور سریع; Remote field eddy current testing; Double wall tube; Wire mesh layer; Steam generator; Fast reactor
Nuclear burning wave in fast reactor with mixed Th-U fuel
Keywords: راکتور سریع; Fast reactor; Intrinsic safety; Negative reactivity feedback; Non-stationary diffusion equation; Nuclear burning wave; Mixed Th-U-Pu fuel cycle
A Preliminary Assessment of the Adoption ofInnovative Technologiesinthe Fast Reactor Cycle Technology Development (FaCT)Project in Japan
Keywords: راکتور سریع; Fast reactor; FaCT,; minor actinides; TRU recovery;
On the use of a moderation layer to improve the safety behavior in sodium cooled fast reactors
Keywords: راکتور سریع; Sodium void effect; SFR; Fast reactor; Uranium-zirconium hydride; Boron carbide;
Benchmark of Advanced Burner Test Reactor model using MCNPX 2.6.0 and ERANOS 2.1
Keywords: راکتور سریع; Transmutation; Transuranic; Minor actinide; MCNPX; ERANOS; Fast reactor
Analysis of the influence of different arrangements for ZrH moderator material on the performance of a SFR core
Keywords: راکتور سریع; Sodium void effect; SFR; Fast reactor; Zirconium hydride
Actinide destruction and power peaking analysis in a 1000Â MWt advanced burner reactor using moderated heterogeneous target assemblies
Keywords: راکتور سریع; Transmutation; Transuranic; Minor actinide; MCNPX; Fast reactor;
A design study on Pb-208 cooled compact CANDLE burning reactor for future nuclear energy supply
Keywords: راکتور سریع; Pb-208 coolant; CANDLE; Fast reactor; Compact; Natural circulation
Destruction rate analysis of transuranic targets in sodium-cooled fast reactor (SFR) assemblies using MCNPX and SCALE 6.0
Keywords: راکتور سریع; Transmutation; Transuranic; Minor actinide; MCNPX; Fast reactor
Turbulent natural convection of sodium in a cylindrical enclosure with multiple internal heat sources: A conjugate heat transfer study
Keywords: راکتور سریع; Turbulent natural convection; Low Prandtl number fluid; Fast reactor; Distributed heat source; Numerical simulation; Water experiments;
Study on small long-life LBE cooled fast reactor with CANDLE burn-up – Part I: Steady state research
Keywords: راکتور سریع; CANDLE; Fast reactor; Small long-life reactor; LBE coolant; Steady state
A rail transportable lead–bismuth cooled reactor
Keywords: راکتور سریع; Lead; Lead–bismuth; Fast reactor; Small nuclear reactor; Transportable nuclear reactor
“CANDLE” burnup regime after LWR regime
Keywords: راکتور سریع; CANDLE burnup; Fast reactor; High burnup; Reprocessing; Enrichment; Uranium resources
Safety design of Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR)
Keywords: راکتور سریع; Fast reactor; Lead–bismuth; Direct contact boiling; Gas lift pump; Safety
Initiation and propagation of nuclear burning wave in fast reactor
Keywords: راکتور سریع; Fast reactor; Inner safety; Intrinsic reactivity feedback; Non-stationary diffusion equation; Nuclear burning wave
Development of high-chromium steel for the sodium-cooled fast reactor in Japan and creep–fatigue assessment of the steel
Keywords: راکتور سریع; Creep–fatigue; Fast reactor; High-Cr steel