Probabilistic evaluation of the leak-tightness function of the nuclear containment structure subjected to internal pressure

Li, Xinbo; Gong, Jinxin

doi:10.1016/j.ress.2023.109684

Cited by 9 publications

(12 citation statements)

References 40 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Strains ε x , ε z , and γ xz are induced by the effects of normal stresses σ x , σ z , and shear stress ν. Reference [15] derived Equation (1) in this study to assess shear stress ν for the given normal stresses σ x and σ z . This method is based on the upper-bound theorem of the plastic limit theory.…”

Section: Comparison With Test Results and Equations In Current Codesmentioning

confidence: 99%

“…In addition to fulfilling general building functions, they are designed to ensure the security of nuclear energy systems. Considering the need to prevent radiation and the leakage of radioactive materials in structures related to nuclear safety [1], walls are often constructed using reinforced concrete. Furthermore, due to the intricate layout of nuclear power equipment, walls in nuclear safety-related structures are primarily low-rise, with an aspect ratio generally not exceeding one.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Lateral Load-Carrying Capacity of Low-Rise Reinforced Concrete Walls in Nuclear Safety-Related Structures

Guo,

Li,

Gong

2023

Buildings

Self Cite

View full text Add to dashboard Cite

Nuclear safety-related structures are crucial for ensuring the safety of nuclear facilities and preventing the leakage of radioactive materials, with the primary structural component being low-rise reinforced concrete (LRC) walls. These walls are required to carry combined in-plane axial and horizontal loads, making the accurate prediction of their lateral load-carrying capacity particularly important. In this study, six LRC walls with aspect ratios between 0.33 and 1 were tested and a model for the prediction of the lateral load-carrying capacity of LRC walls was established based on the observed failure mode and plastic limit theory. The parameter in the model was calibrated using the obtained results in this test along with a database containing 131 walls in the literature. Compared to the equations in the American standard ACI 349 and the French standard RCC-CW, the proposed equation is most suitable for assessing the lateral load-carrying capacity of LRC walls in nuclear safety-related structures. The calculated values of the proposed equation exhibit a ratio closest to 1 when compared to experimental values and possess the minimum degree of variation. The computational results reveal that the proposed equations in this study exhibit superior precision and stability.

show abstract

Section: Comparison With Test Results and Equations In Current Codesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Lateral Load-Carrying Capacity of Low-Rise Reinforced Concrete Walls in Nuclear Safety-Related Structures

Guo,

Li,

Gong

2023

Buildings

Self Cite

View full text Add to dashboard Cite

show abstract

“…In this paper, the primary uncertainties in the NCS are taken into account, including material uncertainty (reflecting the stochastic Fragility curves for the NCS under accident pressure are typically derived using an analytical method, which is fulfilled by performing structural analyses of the NCS with consideration of the associated uncertainties. In this paper, the primary uncertainties in the NCS are taken into account, including material uncertainty (reflecting the stochastic nature of material properties), modeling uncertainty (reflecting the difference between the analytical model and the actual structure), and load uncertainty (reflecting the variability of accident load) [32]. The basic steps of the analytical method for assessing the fragility of the NCS are as follows: Firstly, random samples describing the components of the NCS are generated by random sampling.…”

Section: Fragility Assessment Processmentioning

confidence: 99%

“…Table 2 summarizes the statistical characteristics of the random variables. It is important to note that these statistical parameters are derived from a comprehensive review of the relevant codes and published literature [32,34,35]. Additionally, the compressive strength of concrete is correlated with its elastic modulus and tensile strength, and thus only the compressive strength is treated as a random variable.…”

Section: Fragility Assessment Processmentioning

confidence: 99%

Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion

Li,

Gong

2024

Applied Sciences

Self Cite

View full text Add to dashboard Cite

The steel liner plays a key role in ensuring the leak-tightness of nuclear containment structures (NCSs). Once the liner is subjected to corrosion, its corrosion effects can severely impact the leak-tight function of the NCS, especially in severe accident scenarios. Therefore, evaluating the corrosion effects of the liner is essential to guaranteeing the safe operation of nuclear power plants. This paper presents a probabilistic safety analysis of the NCS under liner corrosion conditions. Firstly, the corrosion mechanism of the liner is elucidated, and a refined simulation method is developed to investigate the localized corrosion effects of the liner. Utilizing a probabilistic finite element method, the fragility of the NCS under loss-of-coolant accident (LOCA) conditions is evaluated. Finally, the leakage risk of the NCS at different degrees of liner corrosion is discussed. The results indicate that liner corrosion has a significant impact on the median pressure capacity and high-confidence–low-probability pressure capacity of the NCS. With the aggravation of liner corrosion, the safety margin of the NCS decreases, and the total probability of failure increases. Within the scope of this paper, the NCS can fulfill the probabilistic safety requirements.

show abstract

“…Fan et al [25] investigated the overpressure vulnerability of the CS using a simplified analytical method and discussed the effect of factors such as concrete strength, steel liner thickness, and reinforcement amount on failure probability. Li et al [26] proposed a probabilistic analysis method accounting for spatial variability in steel liner properties and applied it to evaluate the leakage risk of the CS under internal pressure.…”

Section: Introductionmentioning

confidence: 99%

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

Guo,

Li,

Gong

2024

Buildings

Self Cite

View full text Add to dashboard Cite

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.

show abstract

Probabilistic evaluation of the leak-tightness function of the nuclear containment structure subjected to internal pressure

Cited by 9 publications

References 40 publications

Lateral Load-Carrying Capacity of Low-Rise Reinforced Concrete Walls in Nuclear Safety-Related Structures

Lateral Load-Carrying Capacity of Low-Rise Reinforced Concrete Walls in Nuclear Safety-Related Structures

Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion

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

Contact Info

Product

Resources

About