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Integrating Safety Critical Software System in Probabilistic Safety Assessment
Authors:Gopika Vinod  TV Santosh  RK Saraf  AK Ghosh
Affiliation:Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400085, India
Abstract:In the recent times, computer-based systems are frequently used for protection and control of Nuclear Power Plants (NPPs). In the conventional Probabilistic Safety Assessment (PSA), the contribution from software in these computer-based systems was not given necessary attention. However, from operating experience, it has been found failures in such systems can also result in initiating events that have the potential for leading into Core Damage in the event of unavailability of the respective Engineered Safety Features. The impact of a typical computer-based system on PSA of Indian Nuclear Power Plant is demonstrated.
Keywords:PSA  Probabilistic Safety Assessment  NPP  Nuclear Power Plant  SRGM  Software Reliability Growth Model  CASRE  Computer Aided Software Reliability Estimation  G-O Model  Goel-Okumoto Model  NHPP  Non-Homogenous Poisson Process  J-M Model  Jelinski-Moranda Model  SMERFS  Statistical Modeling and Estimation of Reliability Functions for Software  CDF  Core Damage Frequency  ESF  Engineered Safety Features  LORA  Loss of Regulation Accident  DPHS-RRS  Dual Processor Hot Standby-Reactor Regulating System
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