Ultimate analysis of PWR prestressed concrete containment under long-term prestressing loss

Hu, Hsuan Teh; Lin, Jun

doi:10.1016/j.anucene.2015.10.005

Cited by 21 publications

(4 citation statements)

References 16 publications

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“…The velocity vectors in the bottom outlet of the reactor concrete tank are given in Fig. (12) . As shown in these figures, streamlines around sprays are turbulent.…”

Section: -5 Velocity Vectorsmentioning

confidence: 99%

Thermal-Hydraulic Simulation of Cold Water Spray in a Nuclear Power Plant Containment

Tashakor

Azari

2021

Arab Journal of Nuclear Sciences and Applications

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Sprays play an important role in cooling and decreasing pressure inside the containment of nuclear reactor in emergency situations and excessive pressure of containment. When temperature and pressure exceed 120°C and 2 bars respectively, the sprays cool the inside of PWR containment. The containment spray system is designed to condense the steam to prevent the occurrence of high pressure and temperature, which could lead to disintegration of containment and the leakage of radioactive material to the environment. In this study a simulation of a concrete tank of the reactor (containment) with 250 sprays is accomplished using Ansys Fluent software (18.2). Multiphase mixture model and k-ԑ realizable turbulence model are used to model the reactor. Associated equations are solved using the finite volume method (SIMPLE algorithm with pressure and velocity coupling) in Ansys Fluent software. It is assumed that the flow regime is transient. Results of the thermal-hydraulic function of spraying, which has decreased pressure and temperature, are presented.

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“…The velocity vectors in the bottom outlet of the reactor concrete tank are given in Fig. (12) . As shown in these figures, streamlines around sprays are turbulent.…”

Section: -5 Velocity Vectorsmentioning

confidence: 99%

Thermal-Hydraulic Simulation of Cold Water Spray in a Nuclear Power Plant Containment

Tashakor

Azari

2021

Arab Journal of Nuclear Sciences and Applications

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“…Consequently, the analysis and assessment of the NCS under aging conditions have attracted substantial attention in nuclear engineering. Over the past decades, extensive research efforts have been dedicated to exploring the aging effects on the NCS, including the aging form and aging mechanism of the NCS [1], the long-term behavior and service life prediction of the NCS [2][3][4], the structural response of the aged NCS subjected to overpressure and seismic loads [5,6], a reliability assessment of the aged NCS [7,8], etc. These studies provide significant insights into the establishment of management strategies for aging for nuclear power plants.…”

Section: Introductionmentioning

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

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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.

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“…Noh et al [13] and Shokoohfar et al [14] simulated the 1:4 scale model test carried out by SNL and further explored the mechanical behavior of the CS under thermal-pressure coupled loading. Hu et al [15] examined the ultimate pressure capacity and failure mode of the CS under long-term prestress loss. Huang et al [16] evaluated the long-term performance of the CS under internal pressure by numerical simulation taking into account the time-dependent aging factor.…”

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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Ultimate analysis of PWR prestressed concrete containment under long-term prestressing loss

Cited by 21 publications

References 16 publications

Thermal-Hydraulic Simulation of Cold Water Spray in a Nuclear Power Plant Containment

Thermal-Hydraulic Simulation of Cold Water Spray in a Nuclear Power Plant Containment

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

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