Development of a bayesian belief network model for the software reliability assessment of nuclear digital I and C safety systems - 206
- Department of Mechanical, Aerospace, and Nuclear Engineering, Rensselaer Polytechnic Institute, 110 8th St, Troy, NY (United States)
- School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology, 50, UNIST-gil, Ulsan (Korea, Republic of)
- Brookhaven National Laboratory, Brookhaven Avenue, Upton, NY (United States)
- NUV Technology LLC, 1620 Ridge Haven Run, Alpharetta, GA,(United States)
- Korea Atomic Energy Research Institute, 111, Daedeok-daero, Daejeon (Korea, Republic of)
- U.S. Nuclear Regulatory Commission Washington, DC (United States)
Since the digital instrumentation and control systems are expected to play an important role for the safety systems in nuclear power plants (NPPs), the need has emerged to not only establish a basis for incorporating software behavior into digital I and C system reliability models, but also to quantify the failure probability of the software used in NPP digital protection systems. In this study, a Bayesian belief network (BBN) model is developed to quantitatively assess software reliability by estimating the number of faults in a software program considering its software development life cycle (SDLC). The model structure and parameters are established based on the information applicable to NPP safety-related systems and the evidence used to construct and quantify the BBN model was collected from three stages of expert elicitation. The software failure probability is estimated from the number of residual defects in a software program at the end of SDLC phase. As a case study, the BBN model was applied to quantify the software reliability of a typical digital protection software having the size of 50 function points and having the Medium development and validation and verification (V and V) qualities. The developed model can be applied to estimate the failure probability for both developing and deployed safety-related NPP software, and such results can be used to evaluate the quality of the digital I and C systems in addition to estimating potential reactor risk due to software failure. (authors)
- Research Organization:
- American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 23035331
- Country of Publication:
- United States
- Language:
- English
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