Keywords: PWR، راکتور آب تحت فشار; PSA, Probabilistic Safety Assessment; CCF, Common Cause Failure; CCCG, common cause component group; BE, basic event; PWR, Pressurized Water Reactor; AFWS, Auxiliary Feed Water System; MDPs, motor driven pumps; TDPs, Turbine Driven Pumps; CST, Condensate
مقالات ISI PWR، راکتور آب تحت فشار (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.
Accident mitigation for spent fuel storage in the upper pool of a Mark III containment
Keywords: PWR، راکتور آب تحت فشار; BWR, Boiling Water Reactor; FSAR, Final Safety Analysis Report; HVAC, Heating, Ventilating, and Air Conditioning; PCT, peak cladding temperature; PWR, Pressurized Water Reactor; RB, reactor building; RHR, Residual Heat Removal; SFP, spent fuel pool; STGS,
Short-term pressure and temperature MSLB response analyses for large dry containment of the Maanshan nuclear power station
Keywords: PWR، راکتور آب تحت فشار; PWR, pressurized water reactor; FSAR, Final Safety Analysis Report; MSLB, main steam line break; NSSS, nuclear steam supply system; LOCA, loss of coolant accident; SRP, Standard Review Plan; LOFT, Loss-of-Fluid Test; RPV, reactor pressure vessel; RCS, rea
Analysis of low load transients for the Vandellòs-II NPP: Application to operation and control support
Keywords: PWR، راکتور آب تحت فشار; ANAV, Asociación Nuclear Ascó-Vandellòs; BE, best estimate; Cv, flow coefficient; FW, feed water; NPP, nuclear power plant; PWR, pressurized water reactor; UPC, Technical University of Catalonia
Numerical investigation on practicability of reducing MCST by using grid spacer in a tight rod bundle
Keywords: PWR، راکتور آب تحت فشار; SCWR, supercritical pressure water cooled reactor; PWR, pressurized water reactor; BWR, boiling water reactor; CFD, computational fluid dynamics; HFDVs, hydrodynamically fully-developed values; MCST, maximum cladding surface temperature
Thermal-hydraulics and safety concepts of supercritical water cooled reactors
Keywords: PWR، راکتور آب تحت فشار; ADS, automatic depressurization system; BWR, boiling water reactor; CFD, computational fluid dynamics; DNS, direct numerical simulation; HDR, heissdampfreaktor; HPLWR, high performance light water reactor; PWR, pressurized water reactor; SCWR, supercritic
Debris filtering efficiency and its effect on long term cooling capability
Keywords: PWR، راکتور آب تحت فشار; PWR, pressurized water reactor; KNF, KEPCO nuclear fuel; P-grid, Protective Grid; G-grid, Guardian Grid; OPR1000, optimized power reactor with 1000MWe; APR1400, advanced power reactor with 1400MWe; LTC, long term cooling; LOCA, loss of coolant accident; E
Coupled neutronic thermal–hydraulic transient analysis of accidents in PWRs
Keywords: PWR، راکتور آب تحت فشار; CR, control rod; CPS, control and protection system; FA, fuel assembly; FSAR, Final Safety Assessment Report; IRTRAN, Iranian transient; MTR, material test reactors; PRZ, pressurizer; PWR, pressurized water reactor; TEH, thermo electric heater; T–H, therm
Self-sufficient nuclear fuel technology development and applications
Keywords: PWR، راکتور آب تحت فشار; PWR, Pressurized Water Reactor; PHWR, Pressurized Heavy Water Reactor; KNF, KEPCO Nuclear Fuel; KAERI, Korea Atomic Energy Research Institute; WEC, Westinghouse Electric Company; CHF, critical heat flux; FA, fuel assembly; LTA, Lead Test Assembly; LOCA, L
Experimental investigations of droplet carryover from the separator drum of an air-lift loop simulating a scaled-down AHWR
Keywords: PWR، راکتور آب تحت فشار; Entrainment; Carryover; Air-lift loop; Scaling analysis; AHWRAHWR, Advanced Heavy Water Reactor; BWR, Boiling Water Reactor; FAD, Free Air Delivery; NCL, Natural Circulation Loop; PWR, Pressurized Water Reactor
The study on a statistical methodology for PWR fuel rod internal pressure evaluation
Keywords: PWR، راکتور آب تحت فشار; PWR, pressurized water reactor; RIP, rod internal pressure; OD, outer diameter; IR, inner diameter; DV, dishing volume; PV, plenum volume; FGR, fission gas release; PH, power history
The effect of fuel rod loading speed on spacer grid spring force
Keywords: PWR، راکتور آب تحت فشار; GTRFW, grid-to-rod fretting wear; GTR, grid-to-rod; SG, spacer grid; FIV, fluid-induced vibration; FR, fuel rod; FA, fuel assembly; PWR, pressurized water reactor
A study on the grid-to-rod fretting wear-induced fuel failure observed in the 16×16KOFA fuel
Keywords: PWR، راکتور آب تحت فشار; KNF, Korea Nuclear Fuel; PWR, pressurized water reactor; PHWR, pressurized heavy water reactor; KOFA, Korean Optimized Fuel Assembly; GTRFW, grid-to-rod fretting wear; FIV, fluid-induced vibration; FR, fuel rod; FA, fuel assembly
Two-phase flow regimes and mechanisms of critical heat flux under subcooled flow boiling conditions
Keywords: PWR، راکتور آب تحت فشار; CHF, critical heat flux; DNB, departure from nucleate boiling; PWR, pressurized water reactor
A steam generator model identification and robust H∞ controller design with ν-gap metric for a feedwater control system
Keywords: PWR، راکتور آب تحت فشار; FWCS, feedwater control system; KSNP, Korean standard nuclear power plant; PWR, pressurized water reactor; SG, steam generator; PI, proportional–integral; PID, proportional–integral–derivative
Spent fuel rod splitting due to UO2 oxidation during dry storage: Assessment of the database
Keywords: PWR، راکتور آب تحت فشار; Rod splitting; UO2 oxidation; Dry storageBWR, Boiling Water Reactor; CANDU, Canada Deuterium Uranium; LWR, Light Water Reactor; NPP, Nuclear Power Plant; PWR, Pressurized Water Reactor
Thermal hydraulic behaviors during loss of RHR system at mid-loop operation of Chinese 300 MWe PWR NPP
Keywords: PWR، راکتور آب تحت فشار; NPP, nuclear power plant; PWR, pressurized water reactor; PROV, pressurizer relief valves; RCS, reactor coolant system; RCP, reactor coolant pump; RHR, residual heat removal; RPV, reactor pressure vessel; RWST, refueling water storage tank; SG, steam gene
Development of an advanced PWR fuel for OPR1000s in Korea
Keywords: PWR، راکتور آب تحت فشار; PWR, pressurized water reactor; PHWR, pressurized heavy water reactor; LWR, light water reactor; OPR1000, optimized power reactor 1000 MWe; KNF, Korea Nuclear Fuel; SG, spacer grid; FA, fuel assembly; FR, fuel rod; GT, guide thimble tube; LTA, lead test a
Thermal-hydraulic analysis on the effect of operator action in the loss of shutdown cooling system accident in a PWR
Keywords: PWR، راکتور آب تحت فشار; ADV, atmospheric dump valve; AFW, auxiliary feed water; GF, gravity feed; HPSI, high-pressure safety injection; POS, plant operating state; PSA, probabilistic safety assessment; PWR, pressurized water reactor; PZR, pressurizer; RCP, reactor coolant pump;
Validation and application of the WABE code: Investigations of constitutive laws and 2D effects on debris coolability
Keywords: PWR، راکتور آب تحت فشار; BWR, boiling water reactor; CCFL, counter-current flow limitation; DHF, dryout heat flux; LWR, light water reactor; PWR, pressurized water reactor; RPV, reactor pressure vessel