Analysis of a simplified digital control system for a nuclear power plant pressurizer through the dynamic flowgraph methodology

Reliability, Risk and Safety: Back to the Future

Volumn , Issue , 2010, Pages 1061-1068

  Pinto, J M O ^a   Frutuoso E Melo, P F ^a   Saldanha, P L C ^b,c  

^a FEDERAL UNIVERSITY OF RIO DE JANEIRO   (Brazil)

^b INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES   (Brazil)

^c ABEU Centro Universitário   (Brazil)

Author keywords

[No Author keywords available]

Indexed keywords

CONTROLLED PROCESS; DIGITAL SYSTEM; FAILURE MODES AND EFFECTS ANALYSIS; FAULT-TREES; PROBABILISTIC SAFETY ASSESSMENT; SOFTWARE FAILURE; SYSTEM MODELING;

DIGITAL CONTROL SYSTEMS; FAILURE ANALYSIS; GRAPHIC METHODS; NUCLEAR POWER PLANTS;

SOFTWARE RELIABILITY;

EID: 84861689710     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (12)

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