Keywords: مجمع سوخت; Control Rod Worth; Reactivity Balance; Reactivity Feedback; Small Modular Reactor; Soluble Boron Free; BA; Burnable Absorber; BOC; Beginning of Cycle; CEA; Control Element Assembly; CZP; Cold Zero Power; EOC; End of Cycle; FA; Fuel Assembly; FTC; Fuel Tem
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Keywords: مجمع سوخت; SFP; Spent fuel pool; FA; Fuel assembly; BWR; Boiling water reactor; CFD; Computational fluid dynamics; PSI; Paul Scherrer Institute; LOCA; Loss of coolant accident; Spent fuel pool; Loss of cooling/loss of coolant; Accident conditions; Geysering; SINABEL
Keywords: مجمع سوخت; Fuel assembly; Modelling; Fluid-structure interaction; Added stiffness;
Keywords: مجمع سوخت; Flow boiling; Wall boiling model; Fuel assembly; Critical heat flux;
Keywords: مجمع سوخت; Fuel assembly; Modeling; Fluid-structure interaction; Added stiffness;
Keywords: مجمع سوخت; Abs; Absolute; AO; Axial Offset; CEA; Control Element Assembly; CHCEA; Critical Height of CEA; CRPB; Core Radial Plane Burnup; CRPP; Core Radial Plane Power; DLFO; Daily Load Follow Operation; EOC; End Of Cycle; FA; Fuel Assembly; KNF; Korean Nuclear Fuel
Keywords: مجمع سوخت; Research reactor; Turbulence; Thermal hydraulics; Heat transfer in nuclear reactor; Fuel assembly; Reactor safety; Pool-type research reactor; VVR-M2; VVR-M3; VVR-M5; VVR-ts fuel assemblies;
Keywords: مجمع سوخت; Fuel assembly; Core design; Fast reactors; Structural mechanics;
Keywords: مجمع سوخت; Fuel Assembly; Drop Impact Analysis; Fuel Plate; Research Reactor; Structural Integrity
Keywords: مجمع سوخت; Fuel assembly; Dynamic flow measurements; Fluid–structure interaction
Keywords: مجمع سوخت; Fast reactors; Safety; Autonomous reactivity feedback; Fuel assembly
Keywords: مجمع سوخت; CFD; computational fluid dynamics; FA; fuel assembly; FR; fuel rod; FSI; fluid structure interaction; GT; guide tube (thimble); IRI; incomplete rod cluster assembly insert; MARS; monotone advection and reconstruction scheme; SG; spacer grid; UD; upwind di
Keywords: مجمع سوخت; Reactor core; Fuel assembly; Spacer and mixing grids; Interassembly interaction; Coolant fluid dynamics
Keywords: مجمع سوخت; Spent fuel; Neutron spectrum analysis; 235U and 239Pu content assessment; Helium counter tube; Fission chamber; transmission; Fuel assembly; Residence time
Keywords: مجمع سوخت; Fast-neutron reactors; Fuel assembly; Fuel element bundle models; Cladding temperature calculation; Statistics-based model; Interchannel exchange
Keywords: مجمع سوخت; Reactor unit; Hydraulic resistance; Operational fuel channel; Imitating channel; Thermal hydraulic model of nuclear reactor; Reactor core; Fuel assembly; Modeling scale; Geometry distortion of the model; Euler numbers; Reynolds numbers
Keywords: مجمع سوخت; Nuclear reactor; Fuel assembly; Coolant fluid dynamics; Heat and mass transfer; Mixing spacer grid
Thermal-hydraulic analysis of a superheat BWR design using two fluid model
Keywords: مجمع سوخت; Sub-channel analysis; Fuel assembly; Two-fluid model; Superheat BWR; Annular fuel;
Experimental and CFD analysis of the effects of debris deposition across the fuel assemblies
Keywords: مجمع سوخت; Debris; Fuel assembly; Pressure drop; CFD analysis; Porous medium;
Neutron noise observations in German KWU built PWRs and analyses with the reactor dynamics code DYN3D
Keywords: مجمع سوخت; APSD; Auto-Power Spectral Density; CCF; Cross Correlation Function; FA; Fuel Assembly; FFT; Fast Fourier Transformation; LFNS; Low Frequency Neutron Noise; LHR; Linear Heat Rate; NRMS; Normalized Root Mean Square; PWR; Pressurized Water Reactor;
Feasibility of using Gd2O3 particles in VVER-1000 fuel assembly for controlling excess reactivity
Keywords: مجمع سوخت; Fuel assembly; VVER; Gd2O3 particle; reactivity; power distribution;
Nonlinear empirical model to simulate displacement-dependent structural behavior of a PWR fuel assembly
Keywords: مجمع سوخت; Fuel assembly; Nonlinearity; Slip; Second moment of area; Tangent stiffness; Galerkin method; Newton-Raphson method;
SFR mechanical scenarios and neutron transport transients with CAST3M code
Keywords: مجمع سوخت; SFR; Sodium Fast Reactor; CFSI; Cast3M Fluid-Structure Interaction (tool); CNTT; Cast3M Neutron Transport Tool; CEA; Atomic Energy and Alternative Energies Commission; FSI; Fluid-Structure Interaction; FEM; Finite Element Method; LNP; Lateral Neutron Prot
CFD analysis of the impact of a novel spacer grid with longitudinal vortex generators on the sub-channel flow and heat transfer of a rod bundle
Keywords: مجمع سوخت; Longitudinal vortex generator; Spacer grid; Fuel assembly; Thermal-hydraulic characteristics;
In-service change in the flexural rigidity of the VVER-1000 fuel assemblies
Keywords: مجمع سوخت; Fuel assembly; Fuel rod; VVER; Flexural rigidity; Fuel burnup; Spacer grid; FA skeleton; FA bowing;
Neutronic analysis of a superheat BWR using high performance fuel rod technique
Keywords: مجمع سوخت; Superheat BWR; Annular fuel; Fuel assembly; Neutronic analysis; Steady state;
A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber
Keywords: مجمع سوخت; BigT Burnable Absorber; Critical Boron Concentration; Fuel Assembly; OPR1000; PWR Type Reactor; Serpent
Fluid–structure interaction modelling of a PWR fuel assembly subjected to axial flow
Keywords: مجمع سوخت; Fuel assembly; Modelling; Fluid–structure interaction; Added stiffness
Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method
Keywords: مجمع سوخت; BOL; beginning-of-life; BWR; Boiling Water Reactor; CFD; Computational Fluid Dynamics; CRAM; Chebyshew Rational Approximation Method; ENDF; Evaluated Nuclear Data File; EOL; end-of-life; FA; fuel assembly; FIMA; Fissions per Initial Metal Atom; HTR; High
Application of 3-D coupled code QUABOX/CUBBOX-ATHLET for RBMK-1000 vapor reactivity coefficient measurements
Keywords: مجمع سوخت; AA; additional absorber; CV; check valve; CPS; control and protection system; CR; control rod; DS; drum-separator; ECCS; emergency core cooling system; FA; fuel assembly; FC; fuel channel; FWP; feed water pump; GDH; group distribution header; GRS; Gesells
CFD analysis on subcooled boiling phenomena in PWR coolant channel
Keywords: مجمع سوخت; Subcooled boiling; Fuel assembly; Hot spot; Spacer grid;
LES analysis of the flow in a simplified PWR assembly with mixing grid
Keywords: مجمع سوخت; PWR; Mixing grid; Fuel assembly; Turbulence; LES; HPC;
The core design of ALFRED, a demonstrator for the European lead-cooled reactors
Keywords: مجمع سوخت; CZP; cold zero-power; DBA; design basis accidents; DEC; design extension conditions; DPA; deterministic and phenomenological analyses; ELFR; European lead-cooled fast reactor; FA; fuel assembly; HFP; hot full-power; HZP; hot zero-power; ISAM; integrated s
Evolutionary developments of advanced PWR nuclear fuels and cladding materials
Keywords: مجمع سوخت; PWR; pressurized water reactor; KNF; KEPCO nuclear fuel; KAERI; Korea, Atomic Energy Research Institute; WEC; Westinghouse Electric Company LLC; PF rods; pathfinder rods; LTAs; lead test assemblies; GTRF; grid-to-rod fretting; Opt-Zirlo; optimized Zirlo;
A new SCWR fuel assembly with two-row fuel rods between the hexagonal moderator channels
Keywords: مجمع سوخت; Supercritical water cooled reactor; Fuel assembly; Two-row hexagonal; Neutron physical performance;
MCNPX and HELIOS-2 comparison for the neutronics calculations of a Supercritical Water Reactor HPLWR
Keywords: مجمع سوخت; Supercritical Water Reactor; HPLWR; MCNPX; HELIOS-2; Fuel assembly; Criticality calculations
Thermal–hydraulic analysis of HPLWR fuel assembly cluster
Keywords: مجمع سوخت; Supercritical-pressure; Thermal hydraulic; Sub-channel; Fuel assembly
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure
Keywords: مجمع سوخت; 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
Neutronic analysis of HPLWR fuel assembly cluster
Keywords: مجمع سوخت; Neutronic; HPLWR; Supercritical-pressure; Fuel assembly
Parameters identification by a single point free response measurement
Keywords: مجمع سوخت; Vibrations; Identification; Fuel assembly; Plate
Thermo-mechanical analysis of the prismatic fuel assembly of VHTR in normal operational condition
Keywords: مجمع سوخت; Prismatic Modular Reactor (PMR); Very High Temperature Reactor (VHTR); High Temperature Gas-cooled Reactor (HTGR); Fuel assembly; Thermal stress; Structural integrity;
Measurement of gamma and neutron radiations inside spent fuel assemblies with passive detectors
Keywords: مجمع سوخت; Fuel burn-up; Fuel assembly; Spent fuel; Alanine dosimeter; Track detector
Contributions to the neutronic analysis of a gas-cooled fast reactor
Keywords: مجمع سوخت; Gas-cooled fast reactor; MCNPX; TRIPOLI-4; Fuel assembly; Core reactor; Criticality calculations
Feasibility study of the application of exotic pin for tight-lattice fuel assembly
Keywords: مجمع سوخت; Exotic pin; Cylindrical pin; Tight-lattice; Fuel assembly
Modelling Pressurized Water Reactor cores in terms of porous media
Keywords: مجمع سوخت; Fuel assembly; Nonlinear; Porous; Fluid–structure interaction