Research on evaluation method of NPPs operator’s response plan reliability based on Bayesian network

References

Alvarenga, M. and Melo, P. (2019). A review of the cognitive basis for human reliability analysis. Prog. Nucl. Energy 117: 103050, https://doi.org/10.1016/j.pnucene.2019.103050.Search in Google Scholar

Boring, R.L. and Blackman, H.S. (2007). The origins of the SPAR-H method’s performance shaping factor multipliers. In: 2007 IEEE 8th human factors and power plants and HPRCT 13th annual meeting. IEEE, Monterey, CA, USA, pp. 177–184.10.1109/HFPP.2007.4413202Search in Google Scholar

Carvalho, P.V.R., dos Santos, I.L., and Vidal, M.C.R. (2006). Safety implications of culture and cognitive issues in nuclear power plant operation. Appl Ergon 37: 211–232, https://doi.org/10.1016/j.apergo.2005.03.004.Search in Google Scholar PubMed

Cooper, S.E., Ramey-Smith, A.M., Wreathall, J., Parry, G.W., Bley, D.C., Luckas, W.J., Taylor, J.H., and Barriere, M.T. (1996). A technique for human error analysis (ATHEANA). Technical report NUREG/CR-6350. U.S. Nuclear Regulatory Commission, Rockville, Maryland.10.2172/249298Search in Google Scholar

Embrey, D.E., Humphreys, P., Rosa, E.A., Kirwan, B., and Rea, K. (1984). Maud SLIM: an approach to assessing human error probabilities using structured expert judgment. Volume II: detailed analysis of the technical issues. Technical report NUREG/CR-3518, U.S. Nuclear Regulatory Commission, Rockville, Maryland.Search in Google Scholar

Gertman, D.I., Blackman, H.S., Marble, J.L., Byers, J., Smith, C. (2004). The SPAR-H human reliability analysis method. Technical Report NUREG/CR-6883, US Nuclear Regulatory Commission, Rockville, Maryland.Search in Google Scholar

Grodzinsky, D.M. (1998). General situation of the radiological consequences of the chernobyl accident in Ukraine. In: Imanaka, T. (Ed.). Research activities about the radiological consequences of the chernobyl NPS accident and social activities to assist the sufferers by the accident. Report of an international collaborative work under the research grant of the toyota foundation in 1995-1997. Research reactor institute. Kyoto University, Kyoto, Japan. https://www.rri.kyoto-u.ac.jp/PUB/report/04_kr/img/ekr009.pdf.Search in Google Scholar

Hall, R.E., Fragola, J., and Wreathall, J. (1982). Post event human decision errors: operator action tree/time reliability correlation. Report NUREG/CR-2010. U.S. Nuclear Regulatory Commission, Rockville, Maryland.10.2172/6460666Search in Google Scholar

Hollnagel, E. (1998). Cognitive reliability and error analysis method (CREAM). Elsevier Science Ltd, Oxford.Search in Google Scholar

Huang, F.H. and Hwang, S.L. (2009). Experimental studies of computerized procedures and team size in nuclear power plant operations. Nucl. Eng. Des. 239: 373–380, https://doi.org/10.1016/j.nucengdes.2008.10.009.Search in Google Scholar

Joe, J.C., Shirley, R.B., Mandelli, D., Boring, R.L., and Smith, C.L. (2015). The development of dynamic human reliability analysis simulations for inclusion in risk informed safety margin characterization frameworks. Procedia Manufacturing 3: 1305–1311, https://doi.org/10.1016/j.promfg.2015.07.278.Search in Google Scholar

Kirwan, B. (1992). Human error identification in human reliability assessment. Part 1: overview of approaches. Appl. Ergon. 23: 299–331, https://doi.org/10.1016/0003-6870(92)90292-4.Search in Google Scholar PubMed

Konstandinidou, M., Nivolianitou, Z., Kiranoudis, C., and Markatos, N. (2006). A fuzzy modeling application of cream methodology for human reliability analysis. Reliability Engin & Sys. Safety 91: 706–716, https://doi.org/10.1016/j.ress.2005.06.002.Search in Google Scholar

Lee, S.J., Kim, J., and Jang, S.C. (2011). Human error mode identification for NPP main control room operations using soft controls. J. Nucl. Sci. Technol. 48: 902–910, https://doi.org/10.1080/18811248.2011.9711776.Search in Google Scholar

Li, P.C., Chen, G.H., Dai, L.C., and Zhang, L. (2012). A fuzzy Bayesian network approach to improve the quantification of organizational influences in HRA frameworks. Safety sci. 50: 1569–1583, https://doi.org/10.1016/j.ssci.2012.03.017.Search in Google Scholar

Li, P.C., Zhang, L., Dai, L.C., and Li, X.F. (2017). Study on operator’s SA reliability in digital NPPs. Part 2: data-driven causality model of SA. Ann. Nucl. Energy 109: 185–191, https://doi.org/10.1016/j.anucene.2017.05.011.Search in Google Scholar

O’Hara, J.M., Brown, W.S., Lewis, P.M., and Persensky, P.M.L. (2002). The effects of interface management tasks on crew performance and safety in complex, computer-based systems: detailed analysis, Vol. 2. U.S. Nuclear Regulatory Commission, Rockville, Maryland, Technical Report NUREG/CR-6690.Search in Google Scholar

Rasmussen, J. (1986). Information processing and human machine interaction: an approach to cognitive engineering. Elsevier Science Inc., United States.Search in Google Scholar

Whaley, A.M., Xing, J., Boring, R.L., Hendrickson, S.M.L., Joe, J.C., Le Blanc, K.L., and Morrow, S.L. (2016). Cognitive basis for human reliability analysis. U.S. Nuclear Regulatory Commission, Rockville, Maryland, Technical Report NUREG-2114.Search in Google Scholar

Williams, J.C. (1988). A data-based method for assessing and reducing human error to improve operational performance. In: Conference record for 1988 IEEE fourth conference on human factors and power plants. IEEE, Monterey, CA, USA, pp. 436–450.10.1109/HFPP.1988.27540Search in Google Scholar

Zhang, L., Yang, D.X., and Wang, Y.Q. (2010). Study on the effect of information display on human reliability in digital control room. China Saf. Sci. J. 20: 81–85, (in Chinese).Search in Google Scholar

Zhou, Q., Wong, Y.D., Loh, H.S., and Yuen, K.F. (2018). A fuzzy and Bayesian network CREAM model for human reliability analysis – the case of tanker shipping. Safety sci. 105: 149–157, https://doi.org/10.1016/j.ssci.2018.02.011.Search in Google Scholar