[1] U.S. Nuclear Regulatory Commission, "Reactor concepts manual," 2001, https://www.nrc.gov/docs/ML0230/ML023020519.pdf. Accessed 21 June 2020.
[2] International Atomic Energy Agency (IAEA), "Defense in depth in nuclear safety,” International Nuclear Safety Advisory Group (NSAG), No. 10, Vienna, 1996,https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1013e_web.pdf. Accessed 2 July 2020. [3] B. G. Kim, H. G. Kang, H. E. Kim, and S. J. Lee, "Reliability modeling of digital component in plant protection system with various fault-tolerant techniques,” Nuclear Engineering and Design, vol. 265, pp. 1005– 1015, 2013.
[4] X. X. Guo, Y. B. Liao, D. Y. Xia, and S. Q. Lin, "FMEA analysis for reactor protection system of nuclear power plant", Editorial Board of Nuclear Electronics & Detection Technology, 2015. [5] Y. Bulba, Y. Ponochovny, V. Sklyar, and A. Ivasiuk, "Classification and research of the reactor protection instrumentation and control system functional safety Markov models in a normal operation mode,” 2nd International Workshop on Theory of Reliability and Markov Modeling for Information Technologies, Kyiv, Ukraine, June 2016.
[6] J. Zhao, Y. N. He, P.F.Gu, W. H. Chen, and F.Gao, "Reliability of digital reactor protection system based on extenics,” SpringerPlus, vol. 5, No. 1, 2016. [7] S. Zhou, C. Guo, and D. Li,"Reliability analysis for the reactor protection system of HTR-PM,” 11th International Conference on Reliability, Maintainability and Safety (ICRMS), China, 2016.[8] S. A. Arndt, T. Aldemiret, D. W. Miller, and M.Stovsky, "Methodologies for the probabilistic risk assessment of digital reactor protection and control systems,” Nuclear technology, vol. 159, No.2, pp. 167-191, 2017.
[9] C. Zhuo, Z. Bo, Y. Jian, and S. Jin-long, "Research on the reliability of digital instrumentation and control system of nuclear power plant based ondynamic flow graph methodology,” 25th International Conference on Nuclear Engineering, China, 2017.
[10] D. Li, Z. hao, S. Zhou, and C. Guo, "Application of Monte Carlo methods in reactor protection system reliability research,” 26th International Conference on Nuclear Engineering (ICONE), London, England, 2018.
[11] W. Hao, T. Cong, Z. Shiliang, L. Y. Yuan, and S. Ahmad, "Reliability analysis of the automatic control system of reactor power in nuclear power plant based on DFM,” 24th International Conference on Nuclear Engineering (ICONE), Charlotte, North Carolina, USA, 2016. [12] J. M. O. Pinto, I. B. Gomes, P. L. C. Saldanha, E. B. Furieri, and P. F. F. Melo, In Handbook of Automation and Control Trends, edited by Pedro Ponce.IntechOpen, 2016, Chapter 2.
[13] X. Cao, H. Xiong, C. Guo, D. Li, H. Zhang, and X. Huang, "Petri nets based reliability modeling of reactor protection system considering periodic surveillance test,” 27th International Conference on Nuclear Engineering (ICONE), Japan, 2019. [14] S. Santoso, S. Bakhri, and J. Situmorang, "A Bayesian network approach to estimating software reliability of RSG-GAS reactor protection system,” Atom Indonesia,vol. 45, No. 1, pp. 43 – 49, 2019.
[15] B. Gupta, P. Singh, and L. Singh, "Stability and steady state analysis of control and safety systems of nuclear power plants,” Annals of Nuclear Energy, vol. 147, 2020.
[16] M. Yamashita, S. Miura, M. Fukuda, and M. Hirano, "Reliability analysis of digital reactor protection system,” 12th International Conference on Nuclear Engineering (ICONE), Arlington, Virginia USA, pp. 403-409, April 2004. [17] H. Muta, and K.Muramatsu, "Quantitative modeling of digital reactor protection system using Markov state-transition model,” Journal of Nuclear Science and Technology, vol. 51, No. 9, pp. 1073–1086, 2014. [18] T. Shimodaira, Y. Sato, and K. Suyama, “Estimation of hazardous event rate for repairable 1-out-of-2 safety-related systems based on state transition models,” Transactions of the Institute of Electronics, Information and Communication Engineers, vol. J88-A, No. 8, pp. 962–973, Japanese, 2005. [19] International Atomic Energy Agency (IAEA), "Component reliability data for use in probabilistic safety assessment,” IAEA-TECDOC-478, Vienna, 1988. [20] International Electro-technical Commission (IEC) 61508, "Functional safety of electrical/electronic/programmable electronic safety related systems,” Part 6: Guidelines on the application of IEC 61508-2 and IEC 61508-3, 2010. [21] Japan Nuclear Energy Safety Organization (JNES), "The report of improvement of reliability model of digital reactor protection system,” Japan Nuclear Energy Safety Organization, No. SAE10-013, Tokyo, Japan, 2010. [22] Z. Ma, H. Yoshikawa, and M. Yang, "Reliability model of the digital reactor protection system considering the repair time and common cause failure,” Journal of Nuclear Science and Technology, 2017.
[23] S. A. Eide,M. B. Calley,C. D. Gentillon,T. Wierman, D. Rasmuson, and D. Marksberry, "Reliability study: Westinghouse reactor protection system 1984-1995,” U.S. Nuclear Regulatory Commission RegulationNUREG/CR-5500, vol.2,1998,https://nrcoe.inl.gov/resultsdb/publicdocs/SystemStudies/nureg-cr-5500-vol-2.pdf.Accessed 10 July 2020.