Keywords: از دست دادن تصادف خنک کننده; ADPV; Auto Depressurization Passive Valve; AHWR; Advanced Heavy Water Reactor; BARC; Bhabha Atomic Research Centre; DN; Diametre Nominel; I2S-LWR; Integral Inherently Safe Light Water Reactor; LOCA; Loss of Coolant Accident; PADS; Passive Auto Depressuriz
مقالات ISI از دست دادن تصادف خنک کننده (ترجمه نشده)
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Keywords: از دست دادن تصادف خنک کننده; 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: از دست دادن تصادف خنک کننده; ACP; AC power; APPRCS; Average primary pressure in a reactor coolant system; BN; Bayesian network; CPTs; Conditional probability tables; DST; Dempster-Shafer theory; FCL (1); Flow of coolant in loop 1; FCL (2); Flow of coolant in loop 2; FCL (3); Flow o
Keywords: از دست دادن تصادف خنک کننده; BWR; Boiling Water Reactor; FSAR; Final Safety Analysis Report; HX; Heat Exchanger; PCT; Peak Cladding Temperature; RCLB; Recirculation Line Break; RHR; Residual Heat Removal; SFP; Spent Fuel Pool; SFPACS; Spent Fuel Pool Additional Cooling System; SFPCCS
Keywords: از دست دادن تصادف خنک کننده; Probabilistic Risk Assessment; Risk-Informed Performance-Based Applications; Causal Modeling; Decision Tree; Cost-Benefit Analysis; Uncertainty Analysis; Global Sensitivity Analysis; Risk-Managed Technical Specifications; Risk-Informed Decision Making; AO
Keywords: از دست دادن تصادف خنک کننده; Loss of coolant accident; Research reactor; Siphon; Siphon breaker; Siphon breaker simulation program; LOCA; loss of coolant accident; SBL; siphon breaker line;
Keywords: از دست دادن تصادف خنک کننده; AC; Alternating Current; ADS; Automatic Depressurization System; AWI; Alternative Water Injection; BAF; Bottom of Active Fuel; BWR; Boiling Water Reactor; CCF; Common Cause Failure; CD; Core Damage; CDF; Core Damage Frequency; CST; Condensate Storage Tank
Keywords: از دست دادن تصادف خنک کننده; AC; Alternate Current; AFW; Auxiliary Feed Water; BDBA; Beyond Design Basis Accident; BE; Best Estimate; DBA; Design Basis Accident; DET; Dynamic Event Tree; DOE; Department Of Energy; DPSM; Dynamic Probabilistic Safety Margin; ET; Event Tree; FT; Fault T
Keywords: از دست دادن تصادف خنک کننده; K. Thermal Hydraulics; LOCA; loss of coolant accident; SBL; siphon breaker line;
Keywords: از دست دادن تصادف خنک کننده; Core Concrete Interaction; Loss of Coolant Accident; MELCOR; Passive Autocatalytic Recombiner; Pressurized Water Reactor; Severe Accident;
Keywords: از دست دادن تصادف خنک کننده; Feed-and-bleed operation; Accident sequence; Combined accident; Total loss of feedwater accident; Loss of coolant accident
Keywords: از دست دادن تصادف خنک کننده; Fuzzy Inference System; Fuzzy Neural Network; Genetic Algorithm; Hydrogen Concentration; Loss of Coolant Accident; Severe Accident
Keywords: از دست دادن تصادف خنک کننده; CEA; Commissariat à l'Energie Atomique; DEC; Design Extension Condition; DHR; Decay Heat Removal; ETDR; Experimental and Test Demonstration Reactor; EU FP7; European 7th Framework Programme; GFR; Gas Cooled Fast Reactor; LOCA; Loss of Coolant Accident;
Keywords: از دست دادن تصادف خنک کننده; ADS; automatic depressurization system; AFS; auxiliary feedwater system; ATWS; anticipated transient without scram; BOC; beginning of the cycle; CR; control rod; CSDT; compound system doubling time; DU; depleted uranium; EOC; end of the cycle; FPSR; fissi
Keywords: از دست دادن تصادف خنک کننده; Loss of coolant accident; Severe accident; Support vector classification; Support vector machine; Support vector regression
Keywords: از دست دادن تصادف خنک کننده; ECCS; emergency core cooling system; ICET; integrated chemical effects tests; ICP-AES; inductively coupled plasma atomic emission spectroscopy; LOCA; loss of coolant accident; NaTB; sodium tetraborate; NMR; nuclear magnetic resonance; PHWR; pressurized he
Keywords: از دست دادن تصادف خنک کننده; Nuclear reactor; Loss of coolant accident; Water spray; Droplet vaporization; Moving droplet; Hydrogen-steam-air environment;
Keywords: از دست دادن تصادف خنک کننده; Probabilistic Safety Assessment; Dynamic Event Trees; Accident dynamics; Dependencies; Operator actions; Success criteria; Loss of Coolant Accident
Effect of eccentricity of pressure tube on circumferential temperature distribution of PHWR fuel bundle under postulated accident condition
Keywords: از دست دادن تصادف خنک کننده; PT; Pressure Tube; CT; Calandria Tube; LOCA; Loss of Coolant Accident; ECCS; Emergency Core Cooling System; IPHWR; Indian Pressurized Heavy Water Reactor; LOCA; ECCS; Fuel bundle; PT; CT; Moderator;
Experimental study of small scale siphon breaker to verify Siphon Breaker Simulation Program (SBSP)
Keywords: از دست دادن تصادف خنک کننده; Siphon phenomenon; Siphon breaker; Loss of coolant accident; Research reactor;
Boundary identification between LBLOCA and SBLOCA based on stratification and temperature gradient in two-phase PTS
Keywords: از دست دادن تصادف خنک کننده; BNPP; Bushehr Nuclear Power Plant; CFD; Computational Fluid Dynamics; DCC; Direct Contact Condensation; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; HPIS; High Pressure Injection System; LBLOCA; Large Break Loss OF Coolant Acci
Simulation of the OECD/NEA Sandia Fuel Project Phases I & II ignition tests with DRACCAR
Keywords: از دست دادن تصادف خنک کننده; CA; Central Assembly; DRACCAR; Déformation et Renoyage d'un Assemblage de Crayons Combustibles pendant un Accident de Refroidissement (Deformation and reflooding of a fuel rods assembly during a LOCA accident); FR; Flow Rate; HT; Heat Transfer; IRSN; I
Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations
Keywords: از دست دادن تصادف خنک کننده; BA; Burnable Absorber; BEPU; Best Estimate Plus Uncertainty; BOC; Beginning of Cycle; CASL; Consortium for Advanced Simulation of Light Water Reactors; CD-A; Core Design-Automation; CD-O; Core Design-Optimization; CFD; Computational Fluid Dynamics; CRAM;
Application of regression, variance, and density based global sensitivity methods to integrated VERA-CS and BISON simulations
Keywords: از دست دادن تصادف خنک کننده; BEPU; best estimate plus uncertainty; CASL; consortium for advanced simulation of light water reactors; CIPS; crud induced power shift; CD-A; core design automation; CD-O; core design optimization; COBRA-TF; coolant-boiling in rod arrays-two fluids; FOM;
A study on the robustness of neural network models for predicting the break size in LOCA
Keywords: از دست دادن تصادف خنک کننده; Diagnostic models; Loss of coolant accident; Nuclear power plant; Model robustness;
Sensitivity analysis of VERA-CS and FRAPCON coupling in a multiphysics environment
Keywords: از دست دادن تصادف خنک کننده; BEPU; Best Estimate Plus Uncertainty; CASL; Consortium for Advanced Simulation of Light Water Reactors; CD-A; Core Design Automation; CD-O; Core Design Optimization; COBRA-TF; Coolant-Boiling in Rod Arrays-Two Fluids; EOC; End Of Cycle; FOM; Figure Of Mer
Full length channel Pressure Tube sagging under completely voided full length pressure tube of an Indian PHWR
Keywords: از دست دادن تصادف خنک کننده; PT; Pressure Tube; CT; Calandria Tube; LOCA; Loss of Coolant Accident; ECCS; Emergency Core Cooling System; CANDU; CANada Deuterium Uranium; PHT; primary heat transport; PHWR; Pressurized Heavy Water Reactor; LOCA; Sagging; Pressure Tube; Calandria Tube;
High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding
Keywords: از دست دادن تصادف خنک کننده; Zirconium alloy; Loss of coolant accident; Weight gain; Crack; Breakaway oxidation;
Station black out concurrent with PORV failure using a Generic Pressurized Water Reactor simulator
Keywords: از دست دادن تصادف خنک کننده; AFAS-T; Auxiliary Feed Water Actuation for Turbine-driven Pump; AFW; Auxiliary Feed Water System; APR-1400; Advanced Pressurized Water Reactor (1400 rated power MWe); CCF; Common Cause Failure; DG; Diesel Generator; ETA; Event Tree Analysis; FLC; Factored
Study of clad ballooning and rupture behaviour of Indian PHWR fuel pins under transient heating condition in steam environment
Keywords: از دست دادن تصادف خنک کننده; Loss of coolant accident; Zircaloy-4 cladding; Ballooning and burst behavior; Indian pressurized heavy water reactor; Oxidation;
Methods of applying nuclear simulation technology to the dynamic site testing of digital I&C system-â
¡: DCS-testing methods
Keywords: از دست دادن تصادف خنک کننده; BFV; bypass feedwater valve; BUP; backup panel; DCS; digital distributed I&C system; ECP; emergency control panel; FP; full power; FWS; main feedwater system; HIL; hardware-in-the-loop; HMI; human machine interface; LOCA; loss of coolant accident; I&C; in
Verification of AP1000® low-margin PRA sequences based on best-estimate calculations
Keywords: از دست دادن تصادف خنک کننده; 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
Estimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA condition
Keywords: از دست دادن تصادف خنک کننده; Loss of coolant accident; Steam oxidation; Oxide layer; α-Zr(O) layer; Cladding embrittlement; Ring tension test;
Development, validation and application of multi-point kinetics model in RELAP5 for analysis of asymmetric nuclear transients
Keywords: از دست دادن تصادف خنک کننده; D. Reactor engineering; ASDV; atmospheric steam dump valve; ECCS; emergency core cooling system; IRV; instrumented relief valve; IQS; improved quasi-static; LOCA; loss of coolant accident; LORA; loss of regulation accident; LWR; light water reactor; NPP;
Study of the response of Zircaloy- 4 cladding to thermal shock during water quenching after double sided steam oxidation at elevated temperatures
Keywords: از دست دادن تصادف خنک کننده; Loss of coolant accident; Steam oxidation; Prior β-Zr; Thermal shock; Microhardness;
OECD/NEA Sandia Fuel Project phase I: Benchmark of the ignition testing
Keywords: از دست دادن تصادف خنک کننده; 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
Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline
Keywords: از دست دادن تصادف خنک کننده; Fire spray system; Severe accident mitigation; Severe Accident Management Guideline; ACC; Accumulator; ADS; Automatic Depressurization System; CA; Computational Aid; CMT; Core Makeup Tank; CSE; Containment Systems Experiment; CSS; Containment Spray System
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC
Keywords: از دست دادن تصادف خنک کننده; 1D; one-dimensional; ABWR; Advanced Boiling Water Reactor; BOP; Balance of Plant; BWR; Boiling Water Reactor; CST; condensate storage tank; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; FWLB; feedwater line break; HPCF; High Pre
Study of oxide and α-Zr(O) growth kinetics from high temperature steam oxidation of Zircaloy-4 cladding
Keywords: از دست دادن تصادف خنک کننده; Loss of coolant accident; Steam oxidation; Oxide growth; α-Zr(O) growth; Oxidation kinetics; OXYCON; Zircaloy-4;
Small and Medium sized Reactors (SMR): A review of technology
Keywords: از دست دادن تصادف خنک کننده; 4S; Super-Safe, Small and Simple; AECL; Atomic Energy of Canada Limited; AHWR; Advanced Heavy Water Reactor; ALMCR; Advanced Liquid Metal Cooled Reactor; BWR; Boiling Water Reactor; CANDU; CANadian Deuterium Uranium; CAREM; Central Argentina de Elementos
Long-term pressure and temperature analysis and suppression pool mixing of Lungmen ABWR containment
Keywords: از دست دادن تصادف خنک کننده; 1D; one-dimensional; 2D; two-dimensional; 3D; three-dimensional; ABWR; Advanced Boiling Water Reactor; BOP; Balance of Plant; BWR; Boiling Water Reactor; DID; Defense In Depth; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; FWLB;
Quantitative analysis of the fission product distribution in a damaged fuel assembly using gamma-spectrometry and computed tomography for the Phébus FPT3 test
Keywords: از دست دادن تصادف خنک کننده; PEC; Poste d'Examen Combustible (fuel examination facility); FP; fission product; NDE; non-destructive examination; LOCA; loss of coolant accident; LWR; light water reactor; PWR; pressurised water reaactor; Zry-4; Zircaloy-4;
Steady-state fuel behavior modeling of nitride fuels in FRAPCON-EP
Keywords: از دست دادن تصادف خنک کننده; TD; theoretical density; HM; heavy metal; FGR; fission gas release; BOC; beginning-of-cycle; MOC; middle-of-cycle; EOC; end-of-cycle; LOCA; Loss of Coolant Accident; SD; standard deviation; AE; average fractional error; EOL; end-of-life;
Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project
Keywords: از دست دادن تصادف خنک کننده; BI; base irradiation; BWR; boiling water reactor; DHC; delayed hydride cracking; EPRI; Electric Power Research Institute; FGR; fission gas release; HE; hydrogen embrittlement; KKL; Kernkraftwerk Leibstadt; LOCA; loss of coolant accident; LWR; light water
Simulation of hydrogen distribution in an Indian Nuclear Reactor Containment
Keywords: از دست دادن تصادف خنک کننده; CFD; computational fluid dynamics; BMSKE; buoyancy modified standard k-É; LOCA; loss of coolant accident; RANS; Reynolds Averaged Navier-Stokes; RSM; Reynolds Stress Model;
Analysis of dynamic conditions during thermal transient events for the structural assessment of a nuclear vessel
Keywords: از دست دادن تصادف خنک کننده; Dynamic loading; Finite elements; Master curve; Loss of coolant accident; Pressurised thermal shock
Diagnostic system for identification of accident scenarios in nuclear power plants using artificial neural networks
Keywords: از دست دادن تصادف خنک کننده; Artificial neural networks; Loss of coolant accident; Nuclear power plant; Operator support system