Risk Assessment of NPP Safety in Case of Emergency Situations on Technology

The last accidents of the nuclear power plant (NPP) in Chernobyl and Fukushima give us the new inspiration to verify the safety level of the NPP structures. This paper presents the new requirements to test the safety and reliability of the NPP structures due to the recent accidents in the world. The IAEA in Vienna required in the document ‘Stress tests’ the verification of the safety of the NPP structures under impact of the extreme loads as the earthquakes, the extreme climatic actions and the technology accidents. The new recommendations to load combinations and design criteria were defined. The risk assessment to verify the safety and reliability of the NPP structures based on probabilistic and nonlinear analysis is presented. The uncertainties of material model (behaviour of the reinforcement and liner, concrete cracking and crushing), degradation effects, the loads level (dead and live loads, extreme climatic and accidental temperature and overpressure) as well as other effects following from the inaccuracy of the calculated model and numerical methods were taken into account in the response surface method (RSM) method. The results of the deterministic and probabilistic analysis of the NPP structures are presented.

[1]  AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications , 1986 .

[2]  Juraj Králik.  Probabilistic Safety Analysis of the Nuclear Power Plants in Slovakia , 2010 .

[3]  Miroslav Sýkora,et al.  Assessment of Uncertainties in Mechanical Models , 2013 .

[4]  Juraj Králik,et al.  Probabilistic Nonlinear Analysis of Bubble Tower Structure due to Extreme Pressure and Temperature , 2016 .

[5]  Juraj Králik.  Probabilistic Nonlinear Analysis of the NPP Hermetic Cover Failure due to Extreme Pressure and Temperature , 2017 .

[6]  Juraj Králik.  Deterministic and Probabilistic Analysis of NPP Communication Bridge Resistance Due to Extreme Loads , 2014 .

[7]  Achintya Haldar,et al.  Probability, Reliability and Statistical Methods in Engineering Design (Haldar, Mahadevan) , 1999 .

[8]  K. Bergmeister,et al.  Structural assessment and reliability analysis for existing engineering structures, theoretical background , 2009 .

[9]  Comite Euro-International du Beton,et al.  CEB-FIP Model Code 1990 , 1993 .

[10]  J Kr√°lik.  A RSM method for probabilistic nonlinear analysis of reinforced concrete bubbler tower structure integrity , 2009 .

[11]  CONSIDERATIONS ON THE APPLICATION OF THE IAEA SAFETY REQUIREMENTS FOR THE DESIGN OF NUCLEAR POWER PLANTS , 2014 .

[12]  Zdeněk Kala,et al.  Material and geometrical characteristics of structural steels based on statistical analysis of metallurgical products , 2009 .

[13]  P. E. James T. P. Yao,et al.  Probability, Reliability and Statistical Methods in Engineering Design , 2001 .

[14]  Oldrich Sucharda,et al.  Assessment of loss results by means of multi—criteria analysis , 2011 .

[15]  Milan Holický,et al.  Design characteristics of structural steels based on statistical analysis of metallurgical products , 2004 .

[16]  Kung Szu-Li,et al.  The Design Code , 1985 .

[17]  Igor Pioro,et al.  Introduction: A survey of the status of electricity generation in the world , 2016 .

[18]  Kwang-Il Ahn,et al.  Comparison of Nuclear Power Plant Risk using Dose-based Risk Measure , 2011 .

[19]  Martin Krejsa,et al.  Probabilistic Computational Methods in Structural Failure Analysis , 2015 .

[20]  I. Pioro.  Handbook of Generation-IV Nuclear Reactors , 2017 .

[21]  Zdeněk P. Bažant,et al.  Energetic–statistical size effect simulated by SFEM with stratified sampling and crack band model , 2007 .

[22]  Dimitris Diamantidis,et al.  The Joint Committee on Structural Safety (JCSS) Probabilistic Model Code for New and Existing Structures , 1999 .

[23]  F Pierro,et al.  Structural reliability for containment of VVER 440/213 type , 2014 .

[24]  Juraj Králik.  Experimental and Numerical Analysis of the Hermetic Tightness of NPP Bubble Tower Structure , 2017 .