Fragility analysis and probabilistic safety performance evaluation of nuclear containment structure under local prestressed tendons fracture conditions

Jin, Song; Lan, Tianyun

doi:10.1016/j.anucene.2022.109382

Cited by 8 publications

(2 citation statements)

References 23 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…However, the 1:4 scale model test conducted by SNL found that the measured strains of the prestressing tendons at the time of structural failure of containment often fell below the fracture strains obtained from the laboratory. Referring to the relevant literature [46,47], a threshold value of 3% is adopted in this paper to define the fracture of prestressing tendons. Correspondingly, this failure criterion is abbreviated as SFC-2.…”

Section: Structural Failure Criteriamentioning

confidence: 99%

“…In the overpressure vulnerability analysis of the CS, the internal pressure load serves as the variable, while the stochastic nature of the mechanical properties of materials used in the CS and the uncertainty of the analytical model constitute the primary factors affecting the results of the vulnerability analysis. The overpressure vulnerability curve is typically described using a lognormal distribution [21,31,47], and the failure probability of the CS at a given internal pressure can be expressed as follows:…”

Section: Basic Concept Of Overpressure Vulnerabilitymentioning

confidence: 99%

See 1 more Smart Citation

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

Guo,

Li,

Gong

2024

Buildings

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

Section: Structural Failure Criteriamentioning

confidence: 99%

Section: Basic Concept Of Overpressure Vulnerabilitymentioning

confidence: 99%

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

Guo,

Li,

Gong

2024

Buildings

View full text Add to dashboard Cite

show abstract

Research on the Design and Verification Process of Mechanical Penetrations in Reactor Compartment

Zhang,

Qian,

Wang

et al. 2024

Lecture Notes in Mechanical Engineering

View full text Add to dashboard Cite

Mechanical penetrations, as important pressure pipelines penetrating the reactor compartment, withstand high temperatures and pressures. The current complete design and verification process for mechanical penetrations. This article focuses on the problem of stress concentration and easy damage of the penetration components in the reactor compartment under high temperature and high pressure environment. Combining with the existing regulations of nuclear power plants and ships, finite element analysis method is used to analyze the stress of the penetration components under specific high temperature and high pressure and ship ultimate load coupling. At the same time, based on the simulation analysis results, the structural dimensions of the penetration components are optimized, and a mechanical penetration verification process is designed. The coupled thermal stress results of the penetration indicate that the stress of the penetration is too large at the tail of the sleeve, with the values of primary film stress Pm and primary bending stress Pb being 228.2 and 275.91 MPa, respectively. From this, it can be seemed that there is obvious stress concentration at the junction of the support ring and sleeve, as well as at the transition point of the insulation layer, which is the weakest area of the penetration.

show abstract

Fragility evaluation of nuclear containment structure subjected to earthquake and subsequent internal pressure

Jin,

Jiang,

Wang

et al. 2024

Annals of Nuclear Energy

View full text Add to dashboard Cite

Fragility analysis and probabilistic safety performance evaluation of nuclear containment structure under local prestressed tendons fracture conditions

Cited by 8 publications

References 23 publications

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

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

Research on the Design and Verification Process of Mechanical Penetrations in Reactor Compartment

Fragility evaluation of nuclear containment structure subjected to earthquake and subsequent internal pressure

Contact Info

Product

Resources

About