Keywords: DP, differential pressure; DWO, Density Wave Oscillation; IRIS, International Reactor Innovative and Secure; RELAP, Reactor Excursion and Leak Analysis Program; SG, steam generator; SIET, Società Informazioni Esperienze Termoidrauliche (Company Informatio
مقالات ISI (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.
Modification and application of water film model in COCOSYS for PWR's passive containment cooling
Keywords: COCOSYS, German containment code system; MTE, minimum total energy; PCCS, passive containment cooling system; SG, steam generator
Modelling of fission-product transport in the reactor coolant system
Keywords: FP, fission product; ISTP, international source term programme; CHIP, chemistry of iodine in the primary; RCS, reactor coolant system; LWR, light–water reactor; AECL, Atomic Energy of Canada Ltd.; CANDU, CANada Deuterium Uranium; SG, steam generator; AMMD
Investigation of primary to secondary leakage with loss of primary coolant to the environment through SG SV
Keywords: MSIV, Main Loop Isolating Valves; BZOK, Fast Acting Steam Isolating Valve; SG, steam generator; TSVs, Turbine Stop Valves; SGTR, Steam Generator Tube Rupture; AC, Alternating Current; MCPs, Main Coolant Pumps; PORV, Pressurizer Pilot Operating Relief Valv
Signal processing schemes for Eddy Current Testing of steam generator tubes of nuclear power plants
Keywords: SG, Steam Generator; OD, Outside Defect; FBR, Fast Breeder Reactor; WT, Wall Thinning; NPP, Nuclear Power Plant; ID, Inside Defect; RFECT, Remote Field Eddy Current Testing; PCA, Principal Component Analysis; SP, Support Plate
On the speed of response of an FPGA-based shutdown system in CANDU nuclear power plants
Keywords: SG, steam generator; HIL, hardware-in-the-loop; SDS1, Shutdown System Number 1; I&C, instrument & control; NPP, nuclear power plant; EDA, electronic design automation; LOCA, loss of coolant accident; PLC, programmable logic controller; PDC, programmable d
Experimental CFD grade data for stratified two-phase flows
Keywords: CCFL, counter-current flow limitation; HAWAC, horizontal air/water channel of the FZD; LOCA, loss-of-coolant-accident; PWR, pressurised water reactor; RPV, reactor pressure vessel; SG, steam generator; TOPFLOW, Transient twO Phase FLOW test facility of th
A steam generator model identification and robust H∞ controller design with ν-gap metric for a feedwater control system
Keywords: FWCS, feedwater control system; KSNP, Korean standard nuclear power plant; PWR, pressurized water reactor; SG, steam generator; PI, proportional–integral; PID, proportional–integral–derivative
Semi 2D modeling of the horizontal steam generator PGV-1000 using the RELAP5 code
Keywords: Semi 2D model; Thermal-hydraulic Modeling; VVER-1000 NPP; Horizontal steam generator; RELAP5 codeBNPP, Bushehr Nuclear Power Plant; FSAR, Final Safety Analysis Reports; NPP, Nuclear Power Plant; SG, Steam Generator