Abstract

This paper gives the results of the safety analysis of the nuclear power plant structures in Slovakia in case of the extreme climatic loads. The linear and nonlinear analysis of NPP structures with the reactor VVER 440/213 in the case of the extreme external even is presented. On the base of the meteorological monitoring of the locality the extreme snow load was defined for the return period 104 years. There is showed summary of calculation models and calculation methods for the nonlinear analysis of the structural resistance in system ANSYS. The fragility curves of the critical structure elements were calculated using the FORM method.

Highlights

  • This paper deals with the resistance of the steel hale frame of the nuclear power plant (NPP) in locality Mochovce

  • The definition of the fragility curve of a nuclear power plant structures (NPP) generally represents a crucial step for the level 2 probabilistic safety assessment (PSA L2), where the probability of structure failure can be evaluated as the convolution of the fragility curve with the load curve

  • Hazard model - includes all important initiating events related to hazard analysed includes other significant failures that can lead to CDF - adapted from the internal events, at-power Probabilistic Risk Assessment (PRA) model incorporates unique aspects related to hazard analysed that are different from the at-power, internal events PRA model

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Summary

Introduction

This paper deals with the resistance of the steel hale frame of the nuclear power plant (NPP) in locality Mochovce. The international organization IAEA in Vienna [1] set up the design requirements for the safety and reliability of the NPP structures. PRA provides insights into the strengths and weaknesses of the design and operation of a nuclear power plant. The definition of the fragility curve of a nuclear power plant structures (NPP) generally represents a crucial step for the level 2 probabilistic safety assessment (PSA L2), where the probability of structure failure can be evaluated as the convolution of the fragility curve with the load curve. The assessment of the structural strength of the nuclear power plant has acquired even a greater importance in the framework of postFukushima stress tests where the assessment of the safety margin and off-design conditions [8]. The building of the power block was idealized with a FEM model consisting of 996.917 elements with 444.426 nodes (Figure 2) in program ANSYS

International safety requirements
Methodology of the fragility analysis
Extreme snow load and load combinations
Nonlinear analysis
High confidence of low probability of failure
Conclusion
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