Risk Assessment of Safety Analysis of NPP Structures due to Earthquake Events

Abstract:

This paper presents the probabilistic safety assessment of nuclear power plant (NPP) in Slovakia due to earthquake event. The experiences from the deterministic and probabilistic seismic analyses of the structure resistance are mentioned. On the base of the geophysical and seismological monitoring of locality the peak ground acceleration was defined for the return period 10⁴ years using the Monte Carlo simulations. The synthetic spectrum compatible accelerograms generated in program COMPACEL are presented in comparison with requirements of ASCE4/98 standard.

• Periodical: Applied Mechanics and Materials (Volume 769)
• Pages: 235-240
• DOI: https://doi.org/10.4028/www.scientific.net/AMM.769.235
• Online since: June 2015
• Authors: Juraj Kralik*
• Keywords: ANSYS, Earthquake, NPP, Probability, Safety, Synthetic Accelerogram

References

[1] IAEA, Safety Series 50-SG-D15, Seismic Design and Qualification for Nuclear Power Plants,. IAEA, Vienna, (1992).

DOI: 10.1016/0029-5493(93)90163-4

[2] IAEA, Safety Guide No. 28, Seismic Evaluation of Existing Nuclear Power Plants, IAEA, Vienna, (2003).

[3] J. Kraálik, J. and M. ŠimonovičSimonovic, M., Earthquake response analysis of nuclear power plant buildings with soil-structural interaction. Mathematics and Computers in Simulation 50,. IMACS/Elsevier Science B.V. (1999) pp.227-236.

DOI: 10.1016/s0378-4754(99)00076-2

[4] J. Kraálik, J., Comparison of Probabilistic and Deterministic Assessments for Evaluation of Seismic Safety of Nuclear Power Plants in Slovakia, i. In: First European Conference on Earthquake Engineering and Seismology,. 3-8 September 2006, Geneve, Switzerland,. Pp p.422.

[5] J. Kraálik, J., Safety and Reliability of Nuclear Power Buildings in Slovakia. Earthquake-Impact-Explosion, . Ed. STU Bratislava, 307 pp, (2009).

[6] J. Kraálik, J. and J. Kraálik, J., jr., Seismic Analysis of Reinforced Concrete Frame-Wall Systems Considering Ductility Effects in Accordance to Eurocode. Engineering Structures, . Elsevier, ISSN 0141-0296, Vol. 31, Issue 12, (2009) pp.2865-2872.

DOI: 10.1016/j.engstruct.2009.07.029

[7] J. Kralik, and J. Kralik, jr., Králik,J. and Králik,J. jr., Failure Probability of NPP Communication Bridge under the Extreme Loads, Applied Mechanics and Materials, Vol. 617 (2014).

DOI: 10.4028/www.scientific.net/amm.617.81

[8] I. Neěmec,I. ŠS. SychrováSychrova, I. ŠevčíkSevcik, J. Kabelaácč, L. Weis, Study of a Nuclear Power Plant Containment Damage Caused by Impact of a Plane, iIn: International Refereed Journal of Engineering and Science (IRJES), ISSN (Online) 2319-183X, (Print) 2319-1821, Volume 1, Issue 4 (December 2012), PP. 48-53.

[9] V. Salajka, V.P. Hradil, P.J. Kala, J., Assess of the Nuclear Power Plant Structures Residual Life and Earthquake Resistance, iIn: Proc. The Second International Conference on Engineering and Technology Innovation (ICETI 2012), Kaohsiung, Taiwan, November 02-06, 2012, p.4.

DOI: 10.4028/www.scientific.net/amm.284-287.1247

[10] J. Gottwald, J. andZ. Kala, Z., Sensitivity analysis of tangential digging forces of the bucket wheel excavator SchRs 1320 for different terraces. Journal of Civil Engineering and Management, 18: 5, (2012).

DOI: 10.3846/13923730.2012.719836

[11] N. M. Newmark, N. M. andW. J. Hall, W. J., Development of Criteria for Seismic Review of Selected Nuclear Power Plants. Report NUREG/CR-0098. NRC, Washington, (1975).

[12] NUREG/CR-6926, Evaluation of the Seismic Design Criteria in ASCE/SEI Standard 43-05 for Application to Nuclear Power Plants, BNL-NUREG-77569-2007, U.S. Nuclear Regulatory Commission Washington, DC 20555-0001, Job Code N6112, (2007).

DOI: 10.2172/211545

[13] K. Kotrasovaá, K. E. Kormaniíkovaá, E.I. S. Leoveanu, I. S., Seismic Analysis of Elevated Reservoirs, iIn: proc.: 13th International Multidisciplinary Scientific Geoconference SGEM 2013, Water Resources. Forest, Marine and Ocean Ecosystems, Pub. STEF92 Technology Ltd. Sofia, pp.293-300.

DOI: 10.5593/sgem2013/bc3/s12.037

[14] A. Cipciar, A.P. Labaák, P. Moczo, PM., Kristekovaá, M., Earthquakes in Slovakia and seismic monitoring by the National Network of the Seismic Stations, i. In: Proceedings of the CMEP2, Workshop and Computer Simulation Fatra 2001, 14. -16. 5. 2001, Bratislava, Slovak Republic.

[15] ASCE 4-98, Seismic Analysis of Safety Related Nuclear Structures, ASCE Standard, New York, (1999).

[16] M. Krejsa, P.M. Janas, P. and R. ČajkaCajka, R., Using DOProC Method in Structural Reliability Assessment,. i In: Applied Mechanics and Materials, Vols. 300-301 (2013).

DOI: 10.4028/www.scientific.net/amm.300-301.860

[17] W. T. Lin, W. -T. M. H. , Hsieh, Y. C. M. -H. Wu, C. C.Y. -C. Huang, C. -C., Seismic Analysis of the Condensate Storage Tank in a Nuclear Power Plant. (2012) Journal of Vibroengineering, 14 (3), pp.1021-1030, . 2012. ISSN: 1392-871.

[18] D. Novaák, D.M. Vorřechovskyý, MR. Rusina, R., Small-sample Probabilistic Assessment - software FReET, ICASP 9, 9th International Conference on Applications of Statistics and Probability in Civil Engineering, San Francisco, USA, July 6-9, pp.91-96, (2003).

[19] D. Novaák, DL. Micíča, LB. Teplyý, BM. Vorřechovskyý, MJ. Bucček, JR. Rusina, R. and I. Neěmec, I., Soil-structure interaction stochastic modelling,. iIn: proc. Safety, Reliability and Risk of Structures, Infrastructures and Engineering Systems, Proc. of ICOSSAR 2009, Osaka, Japan, pages 3972-3977. Taylor & Francis Group, London, (2009).

DOI: 10.1201/9781439847657-c75