Keywords: شیر جداسازی بخار اصلی; 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
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Numerical investigation of in-vessel core coolability of PWR through an effective safety injection flow model using MELCOR simulation
Keywords: شیر جداسازی بخار اصلی; 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
Boundary identification between LBLOCA and SBLOCA based on stratification and temperature gradient in two-phase PTS
Keywords: شیر جداسازی بخار اصلی; BNPP; Bushehr Nuclear Power Plant; CFD; Computational Fluid Dynamics; DCC; Direct Contact Condensation; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; HPIS; High Pressure Injection System; LBLOCA; Large Break Loss OF Coolant Acci
An extended BEPU approach integrating probabilistic assumptions on the availability of safety systems in deterministic safety analyses
Keywords: شیر جداسازی بخار اصلی; 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
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC
Keywords: شیر جداسازی بخار اصلی; 1D; one-dimensional; ABWR; Advanced Boiling Water Reactor; BOP; Balance of Plant; BWR; Boiling Water Reactor; CST; condensate storage tank; ECCS; Emergency Core Cooling System; FSAR; Final Safety Analysis Report; FWLB; feedwater line break; HPCF; High Pre
Integral effect test and code analysis on the cooling performance of the PAFS (passive auxiliary feedwater system) during an FLB (feedwater line break) accident
Keywords: شیر جداسازی بخار اصلی; APR+; Advanced Power Reactor Plus; APR1400; Advanced Power Reactor 1400MWe; CL; cold leg; DVI; direct vessel injection; FLB; feedwater line break; HL; hot leg; KAERI; Korea Atomic Energy Research Institute; LSGP; low steam generator pressure; MFIS; main f
Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR
Keywords: شیر جداسازی بخار اصلی; 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