Keywords: Passive system reliability analysis; Correlation analysis; Natural circulation; Thermal-hydraulic model; AP1000;
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Viability of uranium nitride (UN) as annular fuel for AP-1000
Keywords: Uranium nitride; Annular fuel; MCNPX; AP1000;
Calculation and analysis of water activation products source term in AP1000
Keywords: Water activation products; Source term analysis; AP1000; Mechanical shim; Dose rate; 7Li abundance;
An improved simplified method of evaluating severe accident source term in the containment of AP1000
Keywords: Source term; AP1000; ISST; MELCOR; NUREG-1465; SST;
Minor actinide transmutation characteristics in AP1000
Keywords: Minor actinide; Transmutation; AP1000;
Numerical investigation of the separation performance of full-scale AP1000 steam-water separator
Keywords: AP1000; Steam-water separator; Euler-Lagrange approach; Separation efficiency; Numerical simulation;
Simulation study of frequency control characteristics of a generation IIIâ¯+â¯nuclear power plant
Keywords: AP1000; Mathematical modeling; Dynamic simulation; Frequency control;
Transient analysis of AP1000 NPP under the similar Fukushima accident conditions
Keywords: AP1000; Fukushima; Safety analysis;
Three-dimensional simulation of a LBLOCA in an AP1000® containment building
Keywords: AP1000; Containment DBA; GOTHIC; Three-dimensional model;
ADS-IRWST transient evaluation model for AP1000 SBLOCA analysis
Keywords: Automatic Depressurization System; SBLOCA; AP1000;
Feasibility to convert an advanced PWR from UO2 to a mixed U/ThO2 core - Part I: Parametric studies
Keywords: Thorium; PWR; AP1000; Neutronics;
Optimization of AP1000 power control system setpoints using genetic algorithm
Keywords: AP1000; MSHIM; NSGA-II;
Dynamic modeling of AP1000 steam generator for control system design and simulation
Keywords: AP1000; TS model; Thermal hydraulic;
Comparative study on aerosol removal by natural processes in containment in severe accident for AP1000 reactor
Keywords: AP1000; Aerosol; Removal by natural processes; MELCOR; Rapid assessment;
Rod ejection accident analysis for AP1000 with MOX/UOX mixed core loading
Keywords: AP1000; Reactor safety; Reactivity Initiated Accident; Rod ejection accident; UO2/MOX; QUARK;
A sequential-parallel interdependent complement scaling approach with its applications to AP1000 passive containment cooling system
Keywords: Scaling methodology; AP1000; Passive containment; Integrated system;
Verification of AP1000® low-margin PRA sequences based on best-estimate calculations
Keywords: ACC; Accumulator; ADS; Automatic Depressurization System; BE; Best-Estimate; BS; Bounding Sequence; CDF; Core Damage Frequency; CMT; Core Make-up Tank; DSA; Deterministic Safety Analysis; DVI; Direct Vessel Injection; DVILB; Direct Vessel Injection Line B
Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario
Keywords: AP1000; Pressurized Thermal Shock; Thermal hydraulics; Stress analysis; LOCA;
Prediction of falling film evaporation on the AP1000 passive containment cooling system using ANSYS FLUENT code
Keywords: Film evaporation; Containment; AP1000; FLUENT
Control parameter optimization for AP1000 reactor using Particle Swarm Optimization
Keywords: AP1000; MSHIM; Nodal core model; PSO; Control parameter optimization;
Study on working mechanism of AP1000 moisture separator by numerical modeling
Keywords: AP1000; Moisture separator; Droplet-laden flow; Simulation;
Comparative analysis of RIA and LOCA with and without fuel rod behavior modeling in THEATRe code
Keywords: RIA; Fuel rod behavior; Cladding deformation; AP1000; THEATRe code;
Primary loop analysis for a PWR contains Passive Core Cooling System; LOCA and clad rising temperature
Keywords: Reduced Primary Model (RPM); AP1000; LOCA; Passive Core Cooling System (PCCS); Clad temperature; RELAP5
Experimental investigation of upper plenum entrainment in AP1000
Keywords: AP1000; Upper plenum; Liquid entrainment; ADETEL
Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident
Keywords: AP1000; Passive cooling system; Containment safety analysis; GOTHIC;
Modeling of AP1000 and simulation of 10-inch cold leg small break LOCA using the CESAR thermal-hydraulic module of ASTEC
Keywords: AP1000; Small break LOCA; ASTEC; Numerical simulation; Passive safety systems
Development of a simulation platform for dynamic simulation and control studies of AP1000 nuclear steam supply system
Keywords: AP1000; NSSS; Simulation platform; Control systems;
AP1000® SBLOCA simulations with TRACE code
Keywords: AP1000; Passive safety systems; SBLOCA; TRACE;
Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000
Keywords: Clad solid-phase oxidation models; COAC; AP1000; Hydrogen generation rate;
Control simulation and study of load rejection transient for AP1000
Keywords: AP1000; NSSS; Load rejection; Steam dump; Rapid power reduction;
The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC
Keywords: MIDAC-OX; Zirconium oxidation calculating; AP1000; Coolant pump idle
Dynamic simulation and study of Mechanical Shim (MSHIM) core control strategy for AP1000 reactor
Keywords: AP1000; MSHIM strategy; Load follow; Parameter optimization
Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient
Keywords: AP1000; Small break LOCA; ADS-4; Liquid entrainment; RELAP5;
TRU management and 235U consumption minimization in fuel cycle scenarios with AP1000 and VHTRs
Keywords: AP1000; VHTR; Nuclear fuel cycle; Transuranics;
Nodal dynamics modeling of AP1000 reactor for control system design and simulation
Keywords: AP1000; Nodal model; Optimum nodalization scheme; MSHIM;
EXPERIMENTAL STUDY OF CRITICAL HEAT FLUX WITH ALUMINA-WATER NANOFLUIDS IN DOWNWARD-FACING CHANNELS FOR IN-VESSEL RETENTION APPLICATIONS
Keywords: Orientation Angle; Severe Accidents; Nanoparticles; AP1000
The SCDAP/RELAP5 3.2 model of AP1000 on SBLOCA
Keywords: AP1000; SBLOCA; RELAP5; Numerical simulation; Horizontal stratification entrainment
Simulation and analysis on 10-in. cold leg small break LOCA for AP1000
Keywords: AP1000; Small break LOCA; Passive safety; RELAP5; Thermal hydraulic
Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000
Keywords: Fuel rod behavior; Code development; Fuel thermal conductivity; AP1000;
Development of a thermal–hydraulic safety analysis code RETAC for AP1000
Keywords: AP1000; Thermal–hydraulic; Safety analysis; Passive safety; RETAC
High-fidelity system modeling of advanced nuclear energy systems approaching a zero-nuclear-waste limit
Keywords: Fusion–fission hybrid; High-fidelity modeling; AP1000; VHTR; Transuranics
Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA
Keywords: Uncertainty; Fuzzy logic; AP1000; LOCA; Fault tree
Thermal hydraulic phenomena related to small break LOCAs in AP1000
Keywords: AP1000; Small break LOCA; Thermal hydraulic phenomena; Nuclear safety; Passive safety