Keywords: هیدرولیک حرارتی; AHTR; FHR; PIRT; Thermal hydraulics;
مقالات ISI هیدرولیک حرارتی (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
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.
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: هیدرولیک حرارتی; Sodium cooled fast reactor; Thermal hydraulics; Flow characterization; Hexagonal fuel bundle; Comparison of experimental and simulation results;
Keywords: هیدرولیک حرارتی; Thermal hydraulics; Rod bundle; Sub-channel; COBRA;
Keywords: هیدرولیک حرارتی; Pressurizer; Equilibrium and non-equilibrium approach; Control oriented modelling; Thermal hydraulics; RELAP5;
Keywords: هیدرولیک حرارتی; Supercritical carbon dioxide flow; Forced convective heat transfer; Heat transfer correlation; Predictive-corrective method; Thermal hydraulics;
Keywords: هیدرولیک حرارتی; Fast reactor; Fuel pin bundle; Spacer wire; Bundle-duct interaction; Pin bowing; Void swelling; Irradiation creep; Thermal hydraulics; Subchannel;
Keywords: هیدرولیک حرارتی; MSFR; Transient calculation; Neutronics; Thermal hydraulics; Transient Fission Matrix;
Keywords: هیدرولیک حرارتی; HTTR; HTGR; VHTR; Thermal hydraulics; Loss of forced cooling; Safety demonstration tests;
Keywords: هیدرولیک حرارتی; Rod bundles; Circular shaped wires; Trapezoid shaped wires; Thermal hydraulics;
Keywords: هیدرولیک حرارتی; Supercritical; Neutronics; Thermal hydraulics; CO2; Mars;
Keywords: هیدرولیک حرارتی; 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: هیدرولیک حرارتی; Sub-channel; Heaving motion; Rolling motion; Thermal hydraulics; Ocean environment;
Keywords: هیدرولیک حرارتی; Structural mechanics; Thermal hydraulics; Leak area; Leak rate; Accident conditions; Pressure water reactor;
Keywords: هیدرولیک حرارتی; Monte Carlo; Thermal hydraulics; CMFD; Support vector machines; Multipole representation; BEAVRS;
Keywords: هیدرولیک حرارتی; Method of characteristics; Partial differential equations; Nuclear engineering; Reactor physics; Thermal hydraulics; AGENT;
Keywords: هیدرولیک حرارتی; Advanced heavy water reactor; Spatial stabilization; Spatial oscillations; Vectorization; Thermal hydraulics; Mathematical model
The potential impact of Fully Ceramic Microencapsulated (FCM) fuel on thermal hydraulic performance of SMART reactor
Keywords: هیدرولیک حرارتی; FCM fuel; SMART; Reactor dynamics; Thermal hydraulics;
Eigendecomposition model of resistance temperature detector with applications to S-CO2 cycle sensing
Keywords: هیدرولیک حرارتی; Eigendecomposition; Thermal hydraulics; Resistance temperature detector; Super-critical carbon dioxide;
Influence of geometric parameters on thermalhydraulic characteristics of supercritical CO2 in natural circulation loop
Keywords: هیدرولیک حرارتی; Natural circulation loop; Supercritical; Heat transfer deterioration; Thermal hydraulics;
RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators
Keywords: هیدرولیک حرارتی; CANDU; Station Blackout; Crash-cooling; RELAP5; Thermal hydraulics; IBIF;
Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario
Keywords: هیدرولیک حرارتی; AP1000; Pressurized Thermal Shock; Thermal hydraulics; Stress analysis; LOCA;
Modelization of the thermal coupling between the ITER TF coil conductor and the structure cooling circuit
Keywords: هیدرولیک حرارتی; Modelization; Cable-in-conduit conductor; Supercritical helium; Thermal hydraulics; Heat transfer coefficient; Fusion magnets;
Coupling of the 3D neutron kinetic core model DYN3D with the CFD software ANSYS-CFX
Keywords: هیدرولیک حرارتی; Reactors; Simulation; Coupled codes; Thermal hydraulics;
Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part II: Validation of reactor pool design using CFD analyses
Keywords: هیدرولیک حرارتی; SFR; Thermal hydraulics; Scaling analysis; Computational fluid dynamics
Coupled 3D neutronics/thermal hydraulics modeling of the SAFARI-1 MTR
Keywords: هیدرولیک حرارتی; Neutronics; Thermal hydraulics; Modeling; Nuclear reactor; Coupling;
ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles
Keywords: هیدرولیک حرارتی; CANFLEX®; CANadian FLEXible, a registered trademark of AECL and the Korea Atomic Energy Research Institute (KAERI); AECL; Atomic Energy of Canada Limited; AFD; Axial Heat Flux Distribution; ASSERT-PV; Advanced Solution of Subchannel Equations in Reactor
Phenomenology, methods and experimental program for fluoride-salt-cooled, high-temperature reactors (FHRs)
Keywords: هیدرولیک حرارتی; Fluoride-salt-cooled high-temperature reactor (FHR); Thermal hydraulics; Neutronics; Structural mechanics; Nuclear materials; FHR test reactor
An extension of the point kinetics model of MIPR to include the effects of pressure and a varying surface height
Keywords: هیدرولیک حرارتی; Point kinetics; Thermal hydraulics; Aqueous homogeneous reactor; Uranyl nitrate; CRAC;
Modeling of heat transfer and solidification in LIVE L3A experiment
Keywords: هیدرولیک حرارتی; Molten corium; Heat transfer; Thermal hydraulics; Solidification; Mushy zone; Planar front
Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor
Keywords: هیدرولیک حرارتی; Sodium-cooled fast reactor; Subchannel code; Thermal hydraulics
On the numerical approach for simulating reactor thermal hydraulics under seismic conditions
Keywords: هیدرولیک حرارتی; Thermal hydraulics; Seismic condition; Two-phase flow; Simulation; Moving grid; External force;
Developing a computational tool for predicting physical parameters of a typical VVER-1000 core based on artificial neural network
Keywords: هیدرولیک حرارتی; Artificial neural network; Neutronics; Thermal hydraulics; VVER-1000; MDNBR
Thermal hydraulic investigations with different fuel diameters of pebble bed water cooled reactor in CFD simulation
Keywords: هیدرولیک حرارتی; Pebble bed water cooled reactor; Thermal hydraulics; CFD
CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core
Keywords: هیدرولیک حرارتی; CFD; Thermal hydraulics; MTR reactors; Flow blockage; Hot channel; Average channel
Thermal-hydraulic and safety aspects of UO2 fuel for low-power reactors
Keywords: هیدرولیک حرارتی; Low-power research reactors; Thermal hydraulics; Power; Temperature; DBA; MNSRs
Modified COBRA-EN code to investigate thermal-hydraulic analysis of the Iranian VVER-1000 core
Keywords: هیدرولیک حرارتی; Thermal hydraulics; COBRA-EN; VVER-1000; DNBR; EPRI model
Analysis, verification, and benchmarking of the transient thermal hydraulic ITERTHA code for the design of ITER divertor
Keywords: هیدرولیک حرارتی; Thermal hydraulics; Plasma transient events; ITER divertor
TRACE code modeling of the horizontal steam generator of the PACTEL facility and calculation of a loss-of-feedwater experiment
Keywords: هیدرولیک حرارتی; Thermal hydraulics; Modeling; TRACE; Horizontal steam generator; PACTEL
Thermal hydraulic characteristics of air–water two-phase flows in helical pipes
Keywords: هیدرولیک حرارتی; CFD; Helical coil; Two-phase; Air–water; Thermal hydraulics; Two-fluid model
Hydraulics and heat transfer in the IFMIF liquid lithium target: CFD calculations
Keywords: هیدرولیک حرارتی; CFD; IFMIF; Free surface; Liquid metal; Thermal hydraulics; Boiling point
Transient thermal hydraulic modeling and analysis of ITER divertor plate system
Keywords: هیدرولیک حرارتی; Thermal hydraulics; Safety; Fusion; ITER divertor
Steady thermal hydraulic analysis for a molten salt reactor
Keywords: هیدرولیک حرارتی; Molten salt reactor; Thermal hydraulics; Steady characteristics; Numerical simulation; TL426;
Review of research on flow instabilities in natural circulation boiling systems
Keywords: هیدرولیک حرارتی; Natural circulation; Two-phase flow; Boiling water reactor; Boiling channels; Flow instabilities; Thermal hydraulics
Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS
Keywords: هیدرولیک حرارتی; VVER-1000 reactors; Coupled codes; Thermal hydraulics; 3D-neutron kinetics; PARCS; RELAP5