References
- International Atomic Energy Agency. (2010). Development and application of level 1 probabilistic safety assessment for nuclear power plants: Specifi c safety guide. Vienna: IAEA. (SSG-3).
- American Society of Mechanical Engineers. (2009). Standard for level 1/large early release frequency probabilistic risk assessment for nuclear power plant applications, an American National Standard. New York: ASME. (ASME/ANS RA-Sa–2009).
- U.S. Nuclear Regulatory Commission. (2018). An approach for using probabilistic risk assessment in risk-informed decisions on plant-specifi c changes to the licensing basis, Revision 3. Washington D.C.: U.S. NRC. (Regulatory Guide 1.174).
- Fullwood, R. R., & Hall, R. E. (1988). Probabilistic risk assessment in the nuclear power industry, fundamentals and applications. New York: Pergamon Press.
- Henley, E., & Kumamoto, H. (1981). Reliability engineering and risk assessment. Upper Saddle River: Prentice Hall.
- Barlow, R. E., & Proschan, F. (1975). Statistical theory of reliability and life testing: probability models. New York: Holt, Rinehart and Winston, Inc.
- Vesely, W. E., Davis, T. C., Denning, R. S., & Saltos, N. (1983). Measures of risk importance and their applications. Washington D.C.: U.S. NRC. (NUREG/CR-3385).
- Vesely, W. E., Goldberg, F. F., Roberts, N. H., & Haasl, D. F. (1981). Fault tree handbook. Washington D.C.: U.S. NRC. (NUREG-0492).
- Papazoglou, I. A., Bari, R. A., Buslik, A. J., Hall, R. E., Ilberg, D., Samanta, P. K., Teichmann, T., Youngblood, R. W., El-Bassioni, A., Fragola, J., Lofgren, E., & Vesely, W. (1984). Probabilistic safety analysis procedures guide. Washington D.C.: U.S. NRC. (NUREG/CR-2815).
- Cheok, M. C., Parry, G. W., & Sherry, R. R. (1998). Use of importance measures in risk-informed regulatory applications. Reliab. Eng. Syst. Saf., 60(3), 213–226. DOI: S0951-8320(97)00144-0.
- Kim, K., Kang, D. I., & Yang, J.-E. (2005). On the use of the balancing method for calculating component RAW involving CCFs in SSC categorization. Reliab. Eng. Syst. Saf., 87(2), 233–242. DOI: 10.1016/j. ress.2004.04.017.
- Bäckström, O., Krcal, P., & Wang, W. (2016). Two interpretations of the risk increase factor definition. In L. Walls, M. Revie & T. Bedford (Eds.), Risk, reliability and safety: Innovating theory and practice (pp. 2816–2822). Boca Raton, FL: CRC Press.
- Vrbanic, I., Samanta, P., & Basic, I. (2017). Risk importance measures in the design and operation of nuclear power plants. New York: ASME Press.
- Vrbanic, I., Samanta, P., & Basic, I. (2018). Some implications of theoretical relation between RAW and RRW measures on risk reduction strategies. J. Phys. Sci. Appl., 8(3), 38–45. DOI: 10.17265/2159-5348/2018.03.005.
- Nuclear Energy Institute. (2005). 10 CFR 50.69 SSC Categorization guideline, Revision 0. U.S.: NEI. (NEI 00-04).