Failure pressure analysis of a nuclear reactor prestressed concrete containment building

Jiménez, S.; Cornejo, Alejandro; Barbu, Lucía Gratiela; Barbat, Álex H.; Oller, Sergio

doi:10.1016/j.engstruct.2021.112052

Cited by 15 publications

(5 citation statements)

References 13 publications

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“…This code can solve structural dynamic problems with several constitutive material formulations and finite element typologies. The capabilities and accuracy of the PLCD code for the structural analysis of nuclear facilities has been thoroughly validated using experimental data [15] and has been widely used in other similar works on nuclear buildings [18] and by analyzing composite structures [19]. In addition, the GID 4 software, also developed by CIMNE, is employed as pre-and post-processor.…”

Section: Full Soil-structure Modelmentioning

confidence: 99%

Advances in 3d Numerical Simulation of Seismic Response of Safety-Related Nuclear Structures

Rastellini,

Ramirez,

Gonzalez

et al. 2023

Proceedings of the 8th International Conference on Computational Methods in Structural Dynamics and Earthquake Engineering (COM

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In the event of an earthquake at a nuclear power plant, it is vitally important to ensure the survival of personnel and the integrity of high-value equipment. The objective of this study is to analyze the dynamic response of a safety-related nuclear structure subjected to nearmargin seismic signals and to calculate the corresponding in-structure response spectra. A set of seed signals conveniently extracted from databases are selected to generate seismic signals compatible with the target spectrum. These signals are translated to the bedrock level using an iterative deconvolution process. The numerical modeling considers the nonlinearities coming from the structural behavior and from the sliding and rocking at the soilstructure interface. The FEM model includes the soil layers up to the bedrock and cyclic symmetry conditions at the lateral boundaries. Reinforced concrete is modeled using the mixture theory that allows combining non-linear constitutive models of damage and plasticity. The floor spectra are calculated in the positions corresponding to the equipment. Finally, the results show how the non-linearity of the material hardly affects the global response of the analyzed structure. However, the sliding nonlinearity significantly affects the response spectrum of the structure, reducing maximum acceleration peaks.

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Section: Full Soil-structure Modelmentioning

confidence: 99%

Advances in 3d Numerical Simulation of Seismic Response of Safety-Related Nuclear Structures

Rastellini,

Ramirez,

Gonzalez

et al. 2023

Proceedings of the 8th International Conference on Computational Methods in Structural Dynamics and Earthquake Engineering (COM

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show abstract

“…This plasticity model was recently used in the analysis of reinforced concrete structures strengthened with post-tensioned or pre-stressed cable tendons [47], showing interesting results in the plasticity behavior of the material interaction. This model was also employed in the failure analysis of a nuclear power plant reactor subjected to accidental internal pressures, obtaining very satisfactory results [48].…”

Section: Structural Modelmentioning

confidence: 99%

A FEM Structural Analysis of a Francis Turbine Blade Parametrized Using Piecewise Bernstein Polynomials

Arias-Rojas,

Rodríguez-Velázquez,

Cerriteño-Sánchez

et al. 2023

Computation

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Several methodologies have successfully described the runner blade shape as a set of discrete sections joining the hub and shroud, defined by 3D geometrical forms of considerable complexity. This task requires an appropriate parametric approach for its accurate reconstruction. Among them, piecewise Bernstein polynomials have been used to create parametrizations of twisted runner blades by extracting some cross-sectional hydrofoil profiles from reference CAD data to be approximated by such polynomials. Using the interpolating polynomial coefficients as parameters, more profiles are generated by Lagrangian techniques. The generated profiles are then stacked along the spanwise direction of the blade via transfinite interpolation to obtain a smooth and continuous representation of the reference blade. This versatile approach makes the description of a range of different blade shapes possible within the required accuracy and, furthermore, the design of new blade shapes. However, even though it is possible to redefine new blade shapes using the aforementioned parametrization, a remaining question is whether the parametrized blades are suitable as a replacement for the currently used ones. In order to assess the mechanical feasibility of the new shapes, several stages of analysis are required. In this paper, bearing in mind the standard hydraulic test conditions of the hydrofoil test case of the Norwegian Hydropower Center, we present a structural stress–strain analysis of the reparametrization of a Francis blade, thus showing its adequate computational performance in two model tests.

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“…Yan et al [5] investigated the structural behavior and damage mechanism of the CS under accident pressure based on a 3D FE model. Jim'enez et al [17] explored the bearing capacity of the CS under beyond-design basis pressures with the consideration of material aging over the 40-year design life. Li et al [18] systematically discussed the impart of steel liner corrosion on the leak tightness of the CS subjected to overpressure loads by combining a global model and a local refined sub-model.…”

Section: Introductionmentioning

confidence: 99%

Failure Behavior and Vulnerability of Containment Structures Subjected to Overpressure Loads Considering Different Failure Criteria

Guo,

Li,

Gong

2024

Buildings

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This paper investigates the failure behavior and vulnerability of the containment structure (CS) under internal pressure according to different functional and structural failure criteria. Through nonlinear numerical analysis, the deformation of the structure, degree of concrete cracking, and the distribution of stresses and strains in the prestressing tendons and steel liner under different failure criteria are compared. Combined with probabilistic analysis methods, the vulnerability curves, HCLPF capacities, and total failure probabilities of CS determined by different failure criteria are systematically discussed. Results show that there are some differences in the failure behavior and pressure capacity of CS under different failure criteria for both functional and structural failure modes. Under the same failure mode, the variability of the pressure capacities obtained using different criteria is relatively small. Generally, the total failure probabilities of CS subjected to overpressure loads determined by different failure criteria exhibit significant differences. If it is considered that all the investigated failure criteria have a certain ability to predict containment failure, the probabilistic assessment results derived from the functional failure criterion based on the fracture strain of steel liners and the structural failure criterion based on the global strain are deemed to be more reasonable.

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Failure pressure analysis of a nuclear reactor prestressed concrete containment building

Cited by 15 publications

References 13 publications

Advances in 3d Numerical Simulation of Seismic Response of Safety-Related Nuclear Structures

Advances in 3d Numerical Simulation of Seismic Response of Safety-Related Nuclear Structures

A FEM Structural Analysis of a Francis Turbine Blade Parametrized Using Piecewise Bernstein Polynomials

Failure Behavior and Vulnerability of Containment Structures Subjected to Overpressure Loads Considering Different Failure Criteria

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