Keywords: پمپ خنک کننده راکتور; CAP1400; Reactor coolant pump; LOCA; Gas-liquid two-phase; Four quadrants; Gas volume distribution;
مقالات ISI پمپ خنک کننده راکتور (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
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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: پمپ خنک کننده راکتور; Diffuser; Flow Structures; Particle Image Velocimetry; Reactor Coolant Pump; Spherical Casing; Velocity Distribution;
Keywords: پمپ خنک کننده راکتور; Reactor coolant pump; Non-uniform inflow; Pressure pulsation; Rotating speed;
Keywords: پمپ خنک کننده راکتور; Reactor coolant pump; Non-uniform inflow; Pressure pulsation; Experimental investigation;
Keywords: پمپ خنک کننده 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: پمپ خنک کننده راکتور; A/D; analog/digital; BER; bit error rate; BPSK; binary phase shift keying; BSS; Basic Service Set; BW; band width; C/N; carrier to noise ratio; CCW; component cooling water; CCWS; CCW system; CTMT; containment; DSSS; Direct Sequence Spread Spectrum; DTED;
Keywords: پمپ خنک کننده 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
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
Keywords: پمپ خنک کننده راکتور; 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
Thermal-hydraulic analysis of SMART steam generator tube rupture using TASS/SMR-S code
Keywords: پمپ خنک کننده راکتور; SMART; TASS/SMR-S; SGTR; Integral leak; Thermal-hydraulic; CSS; containment spray system; FMHA; flow mixing header assembly; FTC; fuel temperature coefficient; FWIV; feedwater isolation valve; IAPWS; international association for the properties of water s
Complete and homologous pump characteristics for a reactor coolant pump
Keywords: پمپ خنک کننده راکتور; Reactor coolant pump; Complete pump characteristics; Homologous pump characteristics; Pump transients;
Analysis of reactor coolant pump transient performance in primary coolant system during start-up period
Keywords: پمپ خنک کننده راکتور; Primary coolant system; Reactor coolant pump; Performance; Start-up
Investigating the appropriateness of a decision chart to characterize the level of task descriptions in nuclear power plants
Keywords: پمپ خنک کننده راکتور; Task description level; Operation experience; Subjective difficulty; Procedure; Nuclear power plant; CST; Condensate Storage Tank; DEG; Designated means; DETAIL; Detailed level description; EOP; Emergency Operating Procedure; gpm; Gallon per minute; INH;
Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR
Keywords: پمپ خنک کننده راکتور; ADV; atmospheric dump valve; ICI; in-core instrumentation; LPSD; low power and shutdown; LTOP; low temperature over pressure; MSIV; main steam isolation valve; POS; plant operating state; PSA; probabilistic safety assessment; RCP; reactor coolant pump; RC