Keywords: سیستم خنک کننده 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
مقالات ISI سیستم خنک کننده راکتور (ترجمه نشده)
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Keywords: سیستم 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: سیستم 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: سیستم خنک کننده راکتور; AECL; Atomic Energy of Canada Ltd.; BIP; Behaviour of Iodine Programme; CFD; Computational Fluid Dynamics; EDX; Energy Dispersive X-ray; LWR; Light Water Reactor; RCS; reactor coolant system; SARNET; Severe Accident Research Network; STEM; Source Term Eva
Keywords: سیستم خنک کننده راکتور; Reactor coolant system; Optimal design; Sensitivity analyses; Genetic algorithm;
Validation of STRCS code for calculation of fission-product transport in reactor coolant system during severe accidents
Keywords: سیستم خنک کننده راکتور; Source term; Severe accident; Reactor coolant system; STRCS; RELAP/SCDAP;
Systematic hydrogen risk analysis of OPR1000 containment before RPV failure under station blackout scenario
Keywords: سیستم خنک کننده 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: سیستم خنک کننده 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
Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
Keywords: سیستم خنک کننده 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
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
Keywords: سیستم 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
Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
Keywords: سیستم خنک کننده 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
Verification of AP1000® low-margin PRA sequences based on best-estimate calculations
Keywords: سیستم خنک کننده راکتور; 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
An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses
Keywords: سیستم خنک کننده راکتور; BEPU, EBEPU; Probabilistic and deterministic safety analysis; Option 4; Realistic configurations; Safety systems; AFWS; Auxiliary Feed Water System; ATWS; Anticipated Transient Without Scram; BE; Best Estimate; BEPU; Best Estimate Plus Uncertainty methodo
Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor
Keywords: سیستم خنک کننده راکتور; A; activity; AC; alternating current; ASTEC; accident source term evaluation code; BWR; boiling water reactor is a type of light water nuclear reactor; DC; direct current; DOSE; MAAP5 module for the dose calculation; ECCS; emergency core cooling system; E
Steam Line Break investigation at full power reactor for VVER-1000/V320
Keywords: سیستم خنک کننده راکتور; AFWS; auxiliary feed water system; BRU-A; steam dump to atmosphere (SDTAF); BRU-K; steam dump to condenser; CSF; critical safety function; CV; check valve; ECCS; emergency core cooling system; EFW; emergency feed water; EFWS; emergency feed water system;
Investigation of station blackout scenario in VVER440/v230 with RELAP5 computer code
Keywords: سیستم خنک کننده راکتور; AFW; auxiliary feed water; AFWP; auxiliary feed water pump; ALSS; automatic loading sequence system; BAS; Bulgarian Academy of Sciences; BRU-A; steam dumping device on the main steam header; BRU-K; steam dumping device to the condenser; BZOK; fast acting
Multi-objective optimal design for the coolant system of a pressurized power reactor and its validation by the RELAP5/MOD3.2 code
Keywords: سیستم خنک کننده راکتور; Reactor coolant system; Multi-objective optimization; Pareto optimal solutions; RELAP5; Design basic accident
Thermal-hydraulic analysis of SMART steam generator tube rupture using TASS/SMR-S code
Keywords: سیستم 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
Common Risk Target for severe accidents of nuclear power plants based on IAEA INES scale
Keywords: سیستم خنک کننده راکتور; ABWR; Advanced Boiling Water Reactor (GE-Hitachi); ACRP; American Committee for Radiation Protection; (US)AEC; United States Atomic Energy Commission (today US NRC); AIDS; Acquired Immune Deficiency Syndrome; ALARA; As low as reasonably achievable; ALARP;
Investigating the appropriateness of a decision chart to characterize the level of task descriptions in nuclear power plants
Keywords: سیستم 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;
Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests
Keywords: سیستم خنک کننده راکتور; AgInCd; silver-indium-cadmium; BR3; Belgian Reactor 3; BWR; boiling water reactor; B4C; boron carbide; FP; fission product; ISP; International Standard Problem; ISTP; International Source Term Programme; KIT; Karlsruhe Institute of Technology; LWR; li
Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR
Keywords: سیستم 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