Keywords: ملکور; Design Extension Conditions; Research reactor; Heavy water; MELCOR;
مقالات ISI ملکور (ترجمه نشده)
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Keywords: ملکور; Pool scrubbing; Two-phase flow; Severe accident; Aerosol; MELCOR; Wire-mesh sensor;
Keywords: ملکور; Core Concrete Interaction; Loss of Coolant Accident; MELCOR; Passive Autocatalytic Recombiner; Pressurized Water Reactor; Severe Accident;
Keywords: ملکور; DECL; Containment; VVER-1000; CONTAIN 2.0; MELCOR; ANGAR
An equation of state for liquid Pb83Li17
Keywords: ملکور; Lead-lithium; Equation of state; RELAP; MELCOR;
Efficacy analysis of hydrogen mitigation measures of CANDU containment under LOCA scenario
Keywords: ملکور; CANDU; Hydrogen risk; MELCOR; FCVS; Severe accident; Containment failure;
Sensitivity analysis of debris properties in lower plenum of a Nordic BWR
Keywords: ملکور; Severe accident; Nordic BWR; ROAAM; MELCOR;
An improved simplified method of evaluating severe accident source term in the containment of AP1000
Keywords: ملکور; Source term; AP1000; ISST; MELCOR; NUREG-1465; SST;
Systematic hydrogen risk analysis of OPR1000 containment before RPV failure under station blackout scenario
Keywords: ملکور; AACDGS; Alternate AC Diesel Generator System; AICC; Adiabatic Isochoric Complete Combustion; CDF; Core Damage Frequency; CEDM; Control Element Drive Mechanism; CFD; Computational Fluid Dynamics; CSS; Containment Spray System; CV; Control Volume; DBA; Desi
MELCOR modeling and sensitivity analysis of Fukushima Daiichi unit 2 accident considering the latest TEPCO investigations
Keywords: ملکور; Fukushima; Severe accident; Sensitivity analysis; MELCOR;
Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation
Keywords: ملکور; SAMG; In-vessel coolability; Safety injection flow map; Oxidation heat; Core exit temperature; MELCOR; ADV; Atmospheric Dump Valve; AFW; Auxiliary Feed Water; BWR; Boiling Water Reactor; CDV; Condenser Dump Valve; CET; Core Exit Temperature; CV; Control V
Safety evaluation of an extended refilling mode operation after the permanent shutdown of a BWR/4 reactor
Keywords: ملکور; Extended refilling operation; Spent fuel pool; Reactor vessel; Core heat removal; Accident mitigation; Spray cooling; RELAP5; MELCOR;
Improvement of the MELCOR condensation heat transfer model for the thermal-hydraulic analysis of a PWR containment
Keywords: ملکور; Condensation heat transfer; Noncondensable gases; MELCOR; Containment;
Benchmark exercise TH-27 on natural convection with steam injection and condensation inside the extended THAI facility
Keywords: ملکور; Thermohydraulic benchmark; Natural convection; Containment test facility; THAI+; ASTEC; COCOSYS; MELCOR; GASFLOW; CFD;
Prediction of in-vessel debris bed properties in BWR severe accident scenarios using MELCOR and neural networks
Keywords: ملکور; Core relocation; Boiling water reactor; MELCOR; Surrogate model; Artificial neural network;
Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials
Keywords: ملکور; MELCOR; LWR severe accident analysis; Accident tolerant fuel;
Comparative study on aerosol removal by natural processes in containment in severe accident for AP1000 reactor
Keywords: ملکور; AP1000; Aerosol; Removal by natural processes; MELCOR; Rapid assessment;
MELCOR severe accident analysis for a natural circulation small modular reactor
Keywords: ملکور; Severe accident; MELCOR; Natural circulation; SMR; SBLOCA;
Accident tolerant clad material modeling by MELCOR: Benchmark for SURRY Short Term Station Black Out
Keywords: ملکور; Accident tolerant fuel; Fuel performance modeling; MELCOR; Benchmark; Short Term Station Black Out (STSBO); FeCrAl;
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
Keywords: ملکور; CFD; computational fluid dynamics; CHF; critical heat flux; CRP; control rod poison; DCH; direct containment heating; DOE; Department of Energy in the United States; DVI; direct vessel injection; ECCM; effective convectivity-conductivity model; ERVC; exte
Heat up and failure of BWR upper internals during a severe accident
Keywords: ملکور; Upper internals; BWR; Severe accident; MELCOR;
Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident
Keywords: ملکور; Recriticality; Boiling water reactor; Reflooding; MELCOR; SERPENT; Fukushima Daiichi; 1F3; Severe accident;
Implementation and validation of a resuspension model in MELCOR 1.8.6 for fusion applications
Keywords: ملکور; Fusion; Safety; Dust; Resuspension; Force balance model; MELCOR;
Development of One-way-coupling Methodology between Severe Accident Integral Code MELCOR and Monte Carlo Neutron Transport Code SERPENT
Keywords: ملکور; Severe Accident; Recriticality; Monte Carlo; MELCOR; SERPENT; SARCAM;
Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
Keywords: ملکور; A; activity; AC; alternating current; ASTEC; accident source term evaluation code; BWR; boiling water reactor is a type of light water nuclear reactor; DC; direct current; DOSE; MAAP5 module for the dose calculation; ECCS; emergency core cooling system; E
Simulation of the small modular reactor severe accident scenario response to SBO using MELCOR code
Keywords: ملکور; MELCOR; SMR; Station black-out; Severe accident
MELCOR 2.1 analysis of melt behavior in a BWR lower head during LOCA and SBO accident
Keywords: ملکور; Melt behavior; BWR; MELCOR; LOCA; SBO
OECD/NEA Sandia Fuel Project phase I: Benchmark of the ignition testing
Keywords: ملکور; ATHLET-CD; Analysis of THermal-hydraulics of LEaks and Transients with Core Degradation; BIC; boundary and initial conditions; BWR; boiling water reactor; CFD; computational fluid dynamics; CYBL; Cylindrical Boiling; ID; inner diameter; LOCA; loss of cool
Comparative study of the hydrogen generation during short term station blackout (STSBO) in a BWR
Keywords: ملکور; Several accident NPP; BWR; Short-term SBO; MELCOR; SCDAP/RELAP5;
MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000)
Keywords: ملکور; Severe accident simulations; Core safety analyses; MELCOR; China pressurized reactor CPR1000;
A MELCOR model of Fukushima Daiichi Unit 1 accident
Keywords: ملکور; Severe accident; Fukushima accident; MELCOR;
Gas-cooled reactor thermal hydraulic analyses with MELCOR
Keywords: ملکور; MELCOR; HTGR; MHTR; Pressurized/depressurized conduction cool-down; Licensing; BDBA; Beyond Design Basis Accident; CL; Cladding; CV; Control Volume; CVH; Control Volume Hydrodynamics; DBA; Design Basis Accident; DCC; Depressurized Conduction Cool-down; GC
Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism
Keywords: ملکور; PHEBUS FPT1; MELCOR; Core degradation;
Analysis of the accident in the Fukushima Daiichi nuclear power station Unit 3 with MELCOR_2.1
Keywords: ملکور; AWI; Alternative Water Injection; BAF; Bottom of Active Fuel; BSAF; Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station; CAV; cavity in MELCOR; CST; condensate storage tank; COR; core package in MELCOR; CV; control volume (i.e.
Analysis of the THAI Iod-11 and Iod-12 tests: Advancements and limitations of ASTEC V2.0R3p1 and MELCOR V2.1.4803
Keywords: ملکور; AECL; Atomic Energy of Canada Limited; CSNI; Committee on the Safety of Nuclear Installations; FPC; Fission Product Chemistry; EU; European Union; GRS; Gesellschaft für Anlagen- und Reaktorsicherheit; IP; Iodine Pool; IRSN; Institut de Radioprotection et
Severe accident analysis for a typical PWR using the MELCOR code
Keywords: ملکور; CPR1000; MELCOR; Station blackout; Simulation; Thermal analysis;
Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model
Keywords: ملکور; MELCOR; CORA; Core degradation; Hydrogen generating rate; Oxidation model
Analysis of Phébus FP experiments in Korea
Keywords: ملکور; Phébus FP; Core melt progression; Fission product behavior; MELCOR; Iodine; MELCOR-RAIMAAMD, Average Aerodynamic Mean Diameter; AMMD, Aerodynamic Mass Median Diameter; AECL, Atomic Energy of Canada Ltd.; FP, fission products; GSD, Geometric Standard Devia
Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system
Keywords: ملکور; Safety analysis; Ex-vessel LOCA; HCPB TBM; MELCOR; ANSYS
A recent version of MELCOR for fusion safety applications
Keywords: ملکور; Fusion safety; MELCOR; In-vessel water leak; ITER
Development of a code-agnostic computational infrastructure for the dynamic generation of accident progression event trees
Keywords: ملکور; Accident progression event trees; Dynamic event trees; Melcor; Probabilistic risk assessment
Deterministic safety analysis of the reference accidental sequence for the European HCPB TBM system
Keywords: ملکور; ITER; Safety; Blanket development; Beryllium reaction; MELCOR