A Probabilistic Hazard Assessment Framework for Safety-Critical and Control Systems: A Case Study for a Nuclear Power Plant
Author:
Affiliation:
1. Indian Institute of Technology (Banaras Hindu University), Department of Computer Science and Engineering, Varanasi, India
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT16-89
Reference11 articles.
1. STOVSKY M. P. et al. “Dynamic Reliability Modeling of Digital Instrumentation and Control Systems for Nuclear Reactor Probabilistic Risk Assessments,” U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research (2007).
2. Early Prediction of Software Reliability: A Case Study with a Nuclear Power Plant System
3. Design Verification of Instrumentation and Control Systems of Nuclear Power Plants
4. Computing Transition Probability in Markov Chain for Early Prediction of Software Reliability
5. Approach for parameter estimation in Markov model of software reliability for early prediction: a case study
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