Keywords: سیستم حفاظت راکتور; MTR; Material Testing Reactor; SSS; Second Shutdown System; ESF; Engineered Safety Feature; TRR; Tehran Research Reactor; RPS; Reactor Protection System; FSS; First Shutdown System; FOC; First Operating Core; SFE; Standard Fuel Element; CFE; Control Fuel
مقالات ISI سیستم حفاظت 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: سیستم حفاظت راکتور; Multi-State Physics Modeling; Reliability assessment; Three-loop Monte Carlo simulation; Reactor protection system; Resistance temperature detector;
Keywords: سیستم حفاظت راکتور; PSA; Probabilistic Safety Analysis; NPP; Nuclear Power Plant; I&C; Instrumentation and Control; MSPM; Multi-State Physics Model(ing); MCM; Markov Chain Model; MC; Monte Carlo; RTD; Resistance Temperature Detector; RPS; Reactor Protection System; BPL; Bist
Keywords: سیستم حفاظت راکتور; Cyber security; Activity-quality; Architecture analysis; Bayesian network; Reactor protection system; Research reactor;
Keywords: سیستم حفاظت راکتور; AS; Automatic scram; B; Birnbaum importance measure; CCF; Common cause failure; CDF; Core damage frequency; CM; Corrective maintenance; CRMS; Control room manual scram; CT; Completion time; FCDE; Final core damage equation; FFNCT; Fraction of failures no
Sensitivity analysis of APR-1400's Reactor Protection System by using RiskSpectrum PSA
Keywords: سیستم حفاظت راکتور; Reactor Protection System; Probabilistic Safety Assessment; RiskSpectrum; Reliability enhancement;
Cyber Security Risk Evaluation of a Nuclear I&C Using BN and ET
Keywords: سیستم حفاظت راکتور; Activity-Quality; Architecture Analysis; Bayesian Network; Cyber Security; Reactor Protection System; Research Reactor;
An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses
Keywords: سیستم حفاظت 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
Investigation of station blackout scenario in VVER440/v230 with RELAP5 computer code
Keywords: سیستم حفاظت 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
VERONA V6.22 - An enhanced reactor analysis tool applied for continuous core parameter monitoring at Paks NPP
Keywords: سیستم حفاظت راکتور; 2D; two dimensional; 3D; three dimensional; AEKI; Atomic Energy Research Institute (Budapest, Hungary); BOC; beginning of cycle; CFD; computational fluid dynamics; CFX; widely used CFD code; C-PORCA; nodal diffusion code (used for core calculations at Pak
Unavailability and spurious operation probability of k-out-of-n reactor protection systems in consideration of CCF
Keywords: سیستم حفاظت راکتور; Redundant system; k-out-of-n; Unavailability; Spurious operation probability; Common cause failure; Reactor protection system
Assessment methodology for confidence in safety margin for large break loss of coolant accident sequences
Keywords: سیستم حفاظت راکتور; Large break coolant accident; Parameter uncertainty; Latin hypercube sampling; Event tree; Probability distribution; AOO; Anticipated Operational Occurrences; BEPU; Best Estimate Plus Uncertainty Analysis; CD; Core Damage; DBA; Design Basis Accident; HA;