Fragility analysis and probabilistic performance evaluation of nuclear containment structure subjected to internal pressure

Abstract Based on the detailed three-dimensional finite element model of the nuclear containment structure, this study presents fragility analysis and probabilistic performance evaluation of the nuclear containment structure subjected to internal pressure. To realize automatic running of nonlinear finite element analysis of the nuclear containment structure, Python and Matlab scripts are developed. Confidence intervals of fragility parameters are estimated by the statistical inference method and bootstrap method. An analytical method for constructing the confidence interval of the fragility curve is proposed in this study, and confidence interval of the fragility curve predicted by the proposed method is compared with the bootstrap method. Moreover, statistics of the cumulative failure probability of the nuclear containment structure are estimated by bootstrap method and the proposed Taylor series expansion method . Finally, probabilistic safety margins of the nuclear containment structure are evaluated by the median value method and confidence interval method. Results indicate that statistical uncertainty has almost no effect on the mean value of the fragility parameters. However, statistical uncertainty has some effects on the variability of the fragility parameter β S . In general, the influence of statistical uncertainty on fragility parameter β S is greater than that of fragility parameter P m . Confidence intervals of P m estimated by the statistical inference method and bootstrap method are almost the same, and statistical inference method overestimates the confidence interval of fragility parameter β S . The proposed method for constructing confidence interval provides almost the same prediction of the confidence interval of the fragility curve as the bootstrap method. In general, statistics of the cumulative failure probability of the nuclear containment structure calculated by the bootstrap method and the proposed Taylor series expansion method are almost the same. The difference between the safety margin calculated by the median value method and the safety margin with 95% confidence level calculated by confidence interval method is negligible.

[1]  William C. Schnobrich,et al.  Nonlinear finite element analysis of reinforced concrete plates and shells under monotonic loading , 1991 .

[2]  Xu Huang,et al.  Evaluation of CANDU NPP containment structure subjected to aging and internal pressure increase , 2017 .

[3]  Bong Koo Han Reliability assessment and design load factors for reinforced concrete containment structures , 1998 .

[4]  Sang Hoon Noh,et al.  ANALYSIS OF PRESTRESSED CONCRETE CONTAINMENT VESSEL (PCCV) UNDER SEVERE ACCIDENT LOADING , 2008 .

[5]  Hsuan-Teh Hu,et al.  Ultimate analysis of PWR prestressed concrete containment under long-term prestressing loss , 2016 .

[6]  Jonathan Sadeghi,et al.  Structural reliability of pre-stressed concrete containments , 2017 .

[7]  Jinxin Gong,et al.  A simplified fragility analysis methodology for containment structure subjected to overpressure condition , 2020 .

[8]  M. Evans Statistical Distributions , 2000 .

[9]  Ajai S. Pisharady,et al.  Assessment of Ultimate Load Capacity of concrete containment structures against structural collapse , 2017 .

[10]  R. K. Singh,et al.  Over-pressure test on BARCOM pre-stressed concrete containment , 2014 .

[11]  Y. Choun,et al.  Containment performance evaluation of prestressed concrete containment vessels with fiber reinforcement , 2015 .

[12]  Enrico Zio,et al.  Time-dependent reliability analysis of the reactor building of a nuclear power plant for accounting of its aging and degradation , 2021, Reliab. Eng. Syst. Saf..

[13]  A. Schiffer,et al.  Ultimate pressure capacity of nuclear reactor containment buildings under unaged and aged conditions , 2018, Nuclear Engineering and Design.

[14]  Martin Oliver,et al.  Comparison of different Constitutive Models for Concrete in ABAQUS/Explicit for Missile Impact Analyses , 2010 .

[15]  R. K. Singh,et al.  Containment leakage characterization with BARCOM test results for design and over pressure conditions , 2016 .

[16]  N. N. Pujari,et al.  Seismic fragility analysis of a typical Indian PHWR containment: Comparison of fragility models , 2016 .

[17]  M. J. Kolen,et al.  Comparison of Parametric and Nonparametric Bootstrap Methods for Estimating Random Error in Equipercentile Equating , 2008 .

[18]  L. Ibarra Global collapse of frame structures under seismic excitations , 2003 .

[19]  L. P. Sanez,et al.  DISCUSSION OF EQUATION FOR THE STRESS - STRAIN CURVE OF CONCRETE’ BY DESAYI AND KRISHNAN , 1964 .

[20]  Jack W. Baker,et al.  Efficient Analytical Fragility Function Fitting Using Dynamic Structural Analysis , 2015 .

[21]  Lawrence L. Kupper,et al.  Probability, statistics, and decision for civil engineers , 1970 .

[22]  Abhinav Gupta,et al.  Probabilistic risk assessment based model validation method using Bayesian network , 2018, Reliab. Eng. Syst. Saf..

[23]  Thomas T. C. Hsu,et al.  Development of CSMM-based shell element for reinforced concrete structures , 2017 .

[24]  Richard Crowder,et al.  Sizewell ‘B’ - a one tenth scale containment model test for the UK PWR programme , 1991 .

[25]  Jie Li,et al.  Cyclic behavior modeling of reinforced concrete shear walls based on softened damage-plasticity model , 2018, Engineering Structures.

[26]  Seyed Mohsen Hoseyni,et al.  Probabilistic analysis of containment structural performance in severe accidents , 2017, Int. J. Syst. Assur. Eng. Manag..

[27]  Shen Wang Analytical evaluation of the dome-cylinder interface of nuclear concrete containment subjected to internal pressure and thermal load , 2018 .

[29]  Patrick Anderson,et al.  Concentration of plastic strains in steel liners due to concrete cracks in the containment wall , 2008 .

[30]  Xuewu Cao,et al.  Ultimate pressure bearing capacity analysis for the prestressed concrete containment , 2018, Annals of Nuclear Energy.

[31]  Alireza Rahai,et al.  Nonlinear analysis of pre-stressed concrete containment vessel (PCCV) using the damage plasticity model , 2016 .

[32]  Sang Hyo Kim,et al.  Long-term reliability evaluation of nuclear containments with tendon force degradation , 2013 .

[33]  Seyed Mohsen Hoseyni,et al.  Effects of soil-structure interaction on fragility and seismic risk; a case study of power plant containment , 2014 .

[34]  Sang-keun Lee,et al.  Biaxial behavior of plain concrete of nuclear containment building , 2004 .

[35]  Kaspar Willam,et al.  Recent developments in the finite element analysis of prestressed concrete reactor vessels , 1974 .