Keywords: مخزن مخزن راکتور; Steam-water counter-current flow; Partial CCFL correlation; Pressurizer surge line assembly; Advanced passive nuclear reactors; ADS; Automatic Depressurization System; ADS1-3; First to Third Stages of ADS; ADS4; Fourth Stage of ADS; CCF; Counter-Current F
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Keywords: مخزن مخزن راکتور; Thermal aging; Embrittlement; Reactor pressure vessel; Low alloy steel; Neutron diffraction;
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; Pressurized thermal shock; Welding residual stress; Embedded crack;
Keywords: مخزن مخزن راکتور; Irradiation embrittlement; Reactor pressure vessel; Monte-carlo simulation; Cu precipitation; Irradiation correlation;
Keywords: مخزن مخزن راکتور; BWR; boiling water reactor; EAC; environmentally assisted cracking; HE; hydrogen embrittlement; LWR; light water reactor; NPP; nuclear power plant; NRPV; nuclear reactor pressure vessel; PWR; pressurized water reactor; RPV; reactor pressure vessel; VVER;
Keywords: مخزن مخزن راکتور; Fracture analysis; Reactor pressure vessel; XFEM;
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; Thermal-hydraulic analysis; Porous media; SGTR; Computational fluid dynamics;
Keywords: مخزن مخزن راکتور; 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: مخزن مخزن راکتور; Reactor pressure vessel; Integral reactors; I2S-LWR; SMRs;
Keywords: مخزن مخزن راکتور; 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: مخزن مخزن راکتور; As-welded condition; Bead stacking sequence; Reactor pressure vessel; Steam generator; Temper-bead welding; Weld groove geometry;
Keywords: مخزن مخزن راکتور; Positron annihilation spectroscopy; Reactor pressure vessel; Ion implantation;
Keywords: مخزن مخزن راکتور; Cool-Down; Low Temperature Over-Pressurization; Probabilistic Fracture Mechanics; Reactor Pressure Vessel
Keywords: مخزن مخزن راکتور; Pressurized Thermal Shock; RCC-M; Reactor Pressure Vessel; RSE-M; Structural Integrity;
Keywords: مخزن مخزن راکتور; Reactor pressure vessel steel; Temper brittleness; Surveillance specimens; Grain boundary segregation; APT; AES; Phosphorus-carbon competition; Phosphorus segregation kinetics; RPV; reactor pressure vessel; WM; weld metal; BM; base metal; AES; Auger elect
Keywords: مخزن مخزن راکتور; Pressurized thermal shock; Reactor pressure vessel; Constraint loss; Fracture mechanics; Computational fluid dynamics
Keywords: مخزن مخزن راکتور; Support skirt; Reactor pressure vessel; Anchor bolts; Random numbers; Finite element method
Keywords: مخزن مخزن راکتور; 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: مخزن مخزن راکتور; Reactor pressure vessel; Multi-layer welding seam; Specimen orientation; Fracture toughness; Master curve approach; Reference temperature
Keywords: مخزن مخزن راکتور; Diffusion coefficient; Solubility limit; Atom probe; Iron–copper; Reactor pressure vessel
Keywords: مخزن مخزن راکتور; Pressurized thermal shock; Constraint loss; Reactor pressure vessel; In-plane constraint; Out-of-plane constraint
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; Pressurized thermal shock; Probabilistic fracture mechanics; Fracture toughness; Master Curve
Keywords: مخزن مخزن راکتور; Ductile brittle transition; Fracture; Cohesive zone model; Reactor pressure vessel; Steel;
Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: Thermal-hydraulic analysis
Keywords: مخزن مخزن راکتور; AWI; Alternative Water Injection; BAF; Bottom of Active Fuel; BSAF; Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station; CST; Condensate Storage Tank; COR; Core package in MELCOR; CV; Control Volume (i.e. used for hydrodynamic n
A modified correlation between KJIC and Charpy V-notch impact energy of Chinese SA508-III steel at the upper shelf
Keywords: مخزن مخزن راکتور; Fracture toughness; Charpy V-Notch impact energy; Elevated temperature; Reactor pressure vessel; JIC test;
TWOPORFLOW: A two-phase flow porous media code, main features and validation with BWR-relevant bundle experiments
Keywords: مخزن مخزن راکتور; ADI; Alternating Direction Implicit solver; ATHLET; Analysis of Thermal Hydraulics of Leaks and Transient; BFBT; BWR Full-size Fine-mesh Bundle Test benchmark; BICGSTAB; Biconjugate Gradient Stabilized solver; BWR; Boiling Water Reactor; CFD; Computationa
Crack initiation, arrest and tearing assessments of a RPV subjected to PTS events
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; Pressurized thermal shock; Crack initiation; Arrest; Tearing;
Systematic hydrogen risk analysis of OPR1000 containment before RPV failure under station blackout scenario
Keywords: مخزن مخزن راکتور; 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
Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation
Keywords: مخزن مخزن راکتور; 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
Safe reactor depressurization windows for BWR Mark I Station Blackout accident management strategy
Keywords: مخزن مخزن راکتور; 0-D; Zero-Dimensional; 1-D; One-Dimensional; 3-D; Three-Dimensional; AC; Alternating Current; ADS; Automatic Depressurization System; ANS; American Nuclear Society; BDBA; Beyond Design Basis Accident; BWR; Boiling Water Reactor; CFD; Computational Fluid D
Boundary identification between LBLOCA and SBLOCA based on stratification and temperature gradient in two-phase PTS
Keywords: مخزن مخزن راکتور; 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
Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratificatio
Keywords: مخزن مخزن راکتور; Severe accident; VVER; Inverse corium stratification; In-vessel melt retention; Critical heat flux; Reactor pressure vessel; Corium; Melt;
Radiological characterization of the reactor pressure vessel of Trino NPP for dismantling purposes
Keywords: مخزن مخزن راکتور; Decommissioning; Radiological characterization; Reactor pressure vessel; Residual activation; Contamination; Waste inventory;
Phase and structural transformations in VVER-440 RPV base metal after long-term operation and recovery annealing
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; VVER-440; Recovery annealing; Properties recovery; APT; AES; TEM; SEM fractography; Grain boundary segregation; Hardening and non-hardening mechanisms; Mechanical properties;
Severe accident management measures for a generic German PWR. Part II: Small-break loss-of-coolant accident
Keywords: مخزن مخزن راکتور; Severe accident analysis; SBLOCA; PWR; Accident management measures; ACCU; Accumulator; AMM; Accident management measure; ATHLET(-CD); Analyse der Thermohydraulik von Lecks und Transienten/Analysis of thermal-hydraulics of leak and transients (with core d
Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
Keywords: مخزن مخزن راکتور; ACCUs; Accumulators; AM; Accident Management; CET; Core Exit Temperature; CVCS; Chemical and Control Volume System; DGs; Diesel Generators; ECCS; Emergency Core Cooling System; EOPs; Emergency Operating Procedures; FOM; Figure of Merit; FW; Feedwater; HPI
Effects of solute elements on microstructural evolution in Fe-based alloys during neutron irradiation following thermal ageing
Keywords: مخزن مخزن راکتور; Irradiation embrittlement; Solute clusters; Atom probe tomography; Reactor pressure vessel;
Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors
Keywords: مخزن مخزن راکتور; Embrittlement Trend Curve; Pressurized Thermal Shock; Reactor Pressure Vessel; SA533B-1; Transition Temperature Shift;
Evaluation of the energetics of copper-vacancy clusters in Fe
Keywords: مخزن مخزن راکتور; Cu precipitation; Irradiation embrittlement; Reactor pressure vessel; Nucleation free energy; Nucleation path; Damage rate;
Comparison of ASME pressure-temperature limits on the fracture probability for a pressurized water reactor pressure vessel
Keywords: مخزن مخزن راکتور; Probabilistic fracture mechanics; Reactor pressure vessel; Risk-informed; Pressure-temperature limit; Warm-prestressing;
Mechanisms of radiation embrittlement of VVER-1000 RPV steel at irradiation temperatures of (50-400)°C
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; 15Kh2NMFAA class 1 steel; Low temperature irradiation; Elevated temperature irradiation; APT; AES; TEM; Fractographic studies; Grain boundary segregation; Hardening and non-hardening mechanisms; Mechanical properties;
Investigation of SAM measures during selected MBLOCA sequences along with Station Blackout in a generic Konvoi PWR using ASTECV2.0
Keywords: مخزن مخزن راکتور; ACCUs; accumulators; AM; Accident Management; CET; Core Exit Temperature; ECCS; Emergency Core Cooling System; FOM; Figure of Merit; HPIS; High Pressure Injection System; LP; lower plenum; LPIS; Low Pressure Injection System; MBLOCA; Medium Break LOCA; MC
Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
Keywords: مخزن مخزن راکتور; ACCUs; accumulators; AM; accident management; CET; core exit temperature; DGs; diesel generators; ECCS; emergency core cooling system; EFWS; emergency feed water system; FOM; figure of merit; HPIS; high pressure injection system; LP; lower plenum; LPIS; l
Positron annihilation lifetime study of JRQ and JPA irradiated and annealed reactor pressure vessel steels
Keywords: مخزن مخزن راکتور; Positron annihilation spectroscopy; Reactor pressure vessel; Annealing; JRQ; JPA;
Electrical resistivity measurement of Fe-0.6%Cu alloy irradiated by neutrons at 14-19Â K
Keywords: مخزن مخزن راکتور; Reactor pressure vessel; Fe-Cu model alloy; Neutron irradiation; Electrical resistivity; Very low temperature;
HAZOP application for the nuclear power plants decommissioning projects
Keywords: مخزن مخزن راکتور; ALARA; As Low As Reasonably Achievable; AWT; annular water tank; D & D; dismantling and decontamination; ECCS; Emergency Core Cooling System; EU; European Union; FEU; fume extract unit; HAZOP; hazards and operability assessment procedure; HEPA; high effic
Deformation Characteristics and Sealing Performance of Metallic O-rings for a Reactor Pressure Vessel
Keywords: مخزن مخزن راکتور; Deformation Characteristic; Inconel 718; Metallic O-Ring; Reactor Pressure Vessel; Sealing Performance
Interaction between solute atoms and radiation defects in Fe-Ni-Si and Fe-Mn-Si alloys under irradiation with proton ions at low-temperature
Keywords: مخزن مخزن راکتور; Word; Radiation damage; Ion irradiation; Resistivity; Recovery stage; Reactor pressure vessel;
The influence of ppb levels of chloride impurities on the strain-induced corrosion cracking and corrosion fatigue crack growth behavior of low-alloy steels under simulated boiling water reactor conditions
Keywords: مخزن مخزن راکتور; AL; action level of EPRI water chemistry guidelines; ASTM; American Society of Testing and Materials Standards; ASTM E399; test method for plane-strain fracture toughness of metallic materials; BWR; boiling water reactor; CF; corrosion fatigue; CL; consta
An evaluation on the cutting technologies for decommissioning of the tube bundles in the RPV of NPPs
Keywords: مخزن مخزن راکتور; Cutting; Decommissioning; Reactor pressure vessel; Nuclear power plants; Tube bundles;