首页|Design Methodology of Straight Fluid-Conveying Pipes in Nuclear Power Plants Under Stochastic Vibration
Design Methodology of Straight Fluid-Conveying Pipes in Nuclear Power Plants Under Stochastic Vibration
Design Methodology of Straight Fluid-Conveying Pipes in Nuclear Power Plants Under Stochastic Vibration
Stochastic vibration in nuclear power plants can amplify cyclic stress, vibratory displacement, and velocity response of straight fluid-conveying pipes in the primary loop. To address this, a stochastic-vibration mathematical model for clamped-clamped straight pipes under stochastic excitation is established. The model integrates stochastic vibration theory with the finite-element method. Consequently, it systematically quantifies how pipe-support locations and structural parameters influence natural frequencies and stochastic displacement, velocity, and stress responses of fluid-conveying straight pipes. Relocating the support along the span first increases and then decreases the natural frequency, with a peak at node 8. Longer pipes reduce both natural frequency and stress but enlarge displacement and velocity amplitudes. A larger internal diameter suppresses displacement, velocity, and stress while raising natural frequency. Thicker pipe walls attenuate displacement and velocity responses but increase stress and frequency. To optimize performance, we applied a multi-objective genetic algorithm to pipes with adjustable mid-span support under stochastic excitation. Compared to the baseline design, the Pareto-optimal solutions yield a maximum upshift of 28.98% in fundamental frequency, while the Root Mean-Square (RMS) displacement, velocity, and stress are curtailed by up to 24.83%, 24.54%, and 20.55%, respectively. These findings provide a quantitative benchmark for pipe sizing and vibration-mitigation strategies in future nuclear primary piping systems.
核反应堆工程反应堆、核电厂
Stochastic vibrationNuclear power plantStraight Fluid-Conveying PipesDesign methodologyStochastic vibration Nuclear power plant Straight Fluid-Conveying Pipes Design methodology
Lai, Mr. Chao,Qu, Prof. Wei,Peng, Ms. Tian-Lin,Liang, Mr. Yong-Fu,Xia, Prof. Liang-Shu.Design Methodology of Straight Fluid-Conveying Pipes in Nuclear Power Plants Under Stochastic Vibration[EB/OL].(2025-11-02)[2025-11-07].https://chinaxiv.org/abs/202511.00002.点此复制
Stochastic vibration in nuclear power plants can amplify cyclic stress, vibratory displacement, and velocity response of straight fluid-conveying pipes in the primary loop. To address this, a stochastic-vibration mathematical model for clamped-clamped straight pipes under stochastic excitation is established. The model integrates stochastic vibration theory with the finite-element method. Consequently, it systematically quantifies how pipe-support locations and structural parameters influence natural frequencies and stochastic displacement, velocity, and stress responses of fluid-conveying straight pipes. Relocating the support along the span first increases and then decreases the natural frequency, with a peak at node 8. Longer pipes reduce both natural frequency and stress but enlarge displacement and velocity amplitudes. A larger internal diameter suppresses displacement, velocity, and stress while raising natural frequency. Thicker pipe walls attenuate displacement and velocity responses but increase stress and frequency. To optimize performance, we applied a multi-objective genetic algorithm to pipes with adjustable mid-span support under stochastic excitation. Compared to the baseline design, the Pareto-optimal solutions yield a maximum upshift of 28.98% in fundamental frequency, while the Root Mean-Square (RMS) displacement, velocity, and stress are curtailed by up to 24.83%, 24.54%, and 20.55%, respectively. These findings provide a quantitative benchmark for pipe sizing and vibration-mitigation strategies in future nuclear primary piping systems.
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