A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics

Zhang, J.; Wang, M.J.; Zhang, Z.; Sun, Hedong; Wu, Yingwei; Tian, Wenxi; Qiu, Suizheng; Su, G.H.

doi:10.1016/j.nucengdes.2020.110537

Cited by 17 publications

(2 citation statements)

References 102 publications

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“…Husaini, Nurdin Ali, etc., conducted a fracture failure study on the superheater water tube boiler [7]. Zhang, J; Wang, M.J., etc., summarized and commented on the morphologies and thermalhydraulic characteristics in nuclear systems' micro-cracks [8]. The above research reveals that boiler pipe ruptures often originate from small pipe leakages.…”

Section: Introductionmentioning

confidence: 96%

Discriminability Analysis of Characterization Parameters in Micro-Leakage of Turbocharged Boiler’s Evaporation Tube

Xia

Geng

et al. 2022

Energies

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It is extremely dangerous for a turbocharged boiler to have a leakage fault in its vaporization tube. However, early detection and fault diagnosis of micro-leakage faults are very difficult. On the one hand, there are few fault samples that lead to a difficult and intelligent diagnosis. On the other hand, the system fault response characteristics of the characterization parameters in the process are complex and easily confused with the load-changing characteristics. In order to obtain fault samples and identify fault characteristics, a fault simulation model for the micro-leakage of the boiler evaporation tube is established based on the dynamic mathematical model of all working conditions. The model’s effectiveness is verified by typical fault experiments. The dynamic simulation experiments of three kinds of micro-leakage and four kinds of load changing were carried out. Through the analysis of combustion equilibrium and vapor-liquid equilibrium of 14 groups of characterization parameters, it is found that: (1) The reason for the poor discriminability in micro-leakage faults is that most of the characterization parameters tend to balance after 300 s and the dynamic response characteristics are similar to those of load increase. (2) There are four highly distinguishable parameters: the speed of the turbocharger unit, the air supply flow, the flue gas temperature at the superheater outlet, and the furnace pressure. When the micro-leakage fault is triggered, the first three parameters have a large disturbance. They show a trend of decreasing first and then increasing in short periods, unlike normal load-changing conditions. The fourth parameter (furnace pressure) rises abnormally fast after failure. (3) Under the normal working condition of varying loads, the main common parameters take 300 s to stabilize; the common stability parameter values should be recorded because when the micro-leakage fault of evaporation occurs, the steady-state increment of failure is larger than the normal steady increment under variable load conditions, by 2 to 3 times. (4) As the leakage fault increases, the disturbance amplitude of the characteristic parameters becomes larger. In addition, the stability of the steam system becomes worse, and fault discrimination becomes more obvious.

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Section: Introductionmentioning

confidence: 96%

Discriminability Analysis of Characterization Parameters in Micro-Leakage of Turbocharged Boiler’s Evaporation Tube

Xia

Geng

et al. 2022

Energies

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“…Restricting orifices are often used in nuclear power stations' fluid systems to limit the flow of pipelines, but if they are designed incorrectly, they can cause flow-induced vibration [1][2][3]. Long-term operational vibration loads on fluid machinery and pipeline will eventually result in equipment or component fatigue fracture, which leads to leakage [4][5]. The LHSI minimal-flow pipeline of the PWR unit has a flow-induced vibration problem due to the restricting orifice, which could lead to a small branch crack.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Branch Pipes Fracture Condition in Low-Pressure Safety Injection System of PWR

Deng

Chen²,

Zhang³

et al. 2023

J. Phys.: Conf. Ser.

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In the low-pressure injection system (LHSI) of the PWR unit, two branch pipes of the recirculation pipeline are vulnerable to fracture during minimal-flow operation. Flowmaster was used to create a hydraulic model for the LHSI minimal-flow operation and to simulate the branch double-end shear fracture condition in order to predict the leakage flow volume and the water level drop rate of the refueling water storage tank (RWST) in order to analyze the impact of branch pipe fracture on the water leakage of the RWST. According to the study results, there is very little deviation between the operating condition of the system as it actually is and the Flowmaster model, and the leakage volume following branch pipe fracture is considerably less than that of the RWST. Leakage volume per minute is around 0.025% of the RWST’s overall volume, which has negligible influence on the unit’s safety. Based on the results of the simulation, this study suggests LHSI system operation recommendations.

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Application of Machine Learning and Deep Learning Techniques for Corrosion and Cracks Detection in Nuclear Power Plants: A Review

Allah,

Toor,

Shams

et al. 2024

Arab J Sci Eng

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A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: Morphologies and thermal-hydraulic characteristics

Cited by 17 publications

References 102 publications

Discriminability Analysis of Characterization Parameters in Micro-Leakage of Turbocharged Boiler’s Evaporation Tube

Discriminability Analysis of Characterization Parameters in Micro-Leakage of Turbocharged Boiler’s Evaporation Tube

Simulation of Branch Pipes Fracture Condition in Low-Pressure Safety Injection System of PWR

Application of Machine Learning and Deep Learning Techniques for Corrosion and Cracks Detection in Nuclear Power Plants: A Review

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