Nuclear power plant digital system PRA pilot study with the dynamic flowgraph methodology

5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006)

Volumn 2006, Issue , 2006, Pages 261-268

  Yau, Michael ^a   Motamed, Majid ^a   Guarro, Sergio ^a  

^a ASCA Inc   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BENCHMARK SYSTEMS; DIGITAL SYSTEMS; DYNAMIC FLOWGRAPH METHODOLOGY (DFM); SOFTWARE FUNCTIONS;

GRAPH THEORY; HUMAN COMPUTER INTERACTION; MATHEMATICAL MODELS; REGULATORY COMPLIANCE; RISK ASSESSMENT; TREES (MATHEMATICS);

NUCLEAR POWER PLANTS;

EID: 34047141500     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

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2. S. GUARRO, M. YAU, M. MOTAMED, Development of Tools for Safety Analysis of Control Software in Advanced Reactors, NUREG/CR-6465, U.S. Nuclear Regulatory Commission, Washington D.C., (1996).
3. M. YAU, M. WETHERHOLT, S. GUARRO, Safety Analysis and Testing of Critical Space Systems Software, Proc. 4th International Conference on Probabilistic Safety Assessment and Management (PSAM-4), New York City, NY, September 13-18, (1998).
4. M. YAU, G. APOSTOLAKIS, S. GUARRO, "The Use of Prime Implicants in Dependability Analysis of Software Controlled Systems," Reliability Engineering and System Safety, 62, 23, (1998).
5. P.K. LALA, Fault Tolerant and Fault Testable Hardware Design, Prentice Hall International, London, (1985).