Integration of reliability models for nuclear power plant digital instrumentation and control systems into probabilistic risk assessment studies

Tune Aldemir, Don W. Miller, Audeen W. Fentiman, Steven A. Arndt

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

3 Scopus citations

Abstract

Nuclear power plants are now replacing and upgrading aging and obsolete instrumentation and control (I&C) systems with digital systems. For near term applications, a digital I&C system reliability model must be compatible with the structure of current nuclear power plant probabilistic risk assessments (PRAs) which use the static event-tree/faulttree (ET/FT) approach. The limitation of the ET/FT approach in the representation of the differences between the digital I&C systems and their analog counterparts may necessitate the use of dynamic methodologies. The available methodologies for the reliability modeling of digital I&C systems are reviewed. The findings indicate that there is no single methodology currently available that: a) satisfies all the requirements for the reliability modeling digital I&C systems, and, b) is also compatible with the current PRA methodologies. A comparison of the most promising methodologies indicate that using a benchmark problem of interest to nuclear power plants on a full existing scale PRA will help resolve the existing uncertainties with their capabilities.

Original languageEnglish
Title of host publicationAmerican Nuclear Society International Topical Meeting on Probabilistic Safety Analysis, PSA 05
Pages1037-1045
Number of pages9
StatePublished - 2005
Externally publishedYes
EventAmerican Nuclear Society International Topical Meeting on Probabilistic Safety Analysis, PSA 05 - San Francisco, CA, United States
Duration: Sep 11 2005Sep 15 2005

Publication series

NameAmerican Nuclear Society International Topical Meeting on Probabilistic Safety Analysis, PSA 05
Volume2005

Conference

ConferenceAmerican Nuclear Society International Topical Meeting on Probabilistic Safety Analysis, PSA 05
Country/TerritoryUnited States
CitySan Francisco, CA
Period09/11/0509/15/05

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