Abstract
Anti-vibration bars (AVBs) are essential components of a steam generator (SG) and are used to prevent steam generator tubes (SGTs) from vibrating intensely because of flow-induced vibration. However, the contact force generated at contact surfaces between AVBs and tubes can change the natural frequency and wear behavior of the tube. Contact force is represented by clamping force in this study. Considering the effect of the clamping force on the natural frequency and sliding distance of SGT, dynamic wear behavior under different clamping forces was analyzed based on the finite element method, and the natural frequency of the tube was measured in the present work. Moreover, the wear experiment was conducted at room temperature to verify the conclusions of dynamic behavior analysis. The increase in clamping force reduces the sliding distance of SGT, and wear depth affected by both clamping force and sliding distance also decreases.
Highlights
A steam generator (SG) is significant equipment in a pressurized water reactor nuclear power plant through which the heat generated by the nuclear reactor in the primary circuit is transferred to the secondary circuit
The experimental results are represented by a solid line, the simulated results of the tube with supported boundary conditions are represented by dotted lines, and6the of 15 clamped constraints are represented by dashed lines
Wear experiments under different clamping forces were completed to verify the conclusion of dynamic wear behavior analysis based on the finite element method
Summary
A steam generator (SG) is significant equipment in a pressurized water reactor nuclear power plant through which the heat generated by the nuclear reactor in the primary circuit is transferred to the secondary circuit. Steam generator tubes (SGTs) are the contact surface between the primary circuit medium and the secondary circuit medium, which requires high operational reliability. Once the SGT is damaged, it will cause the radioactive material in the primary circuit to overflow, posing a significant threat to the safety of the surrounding environment [1,2]. Once the wear depth of the SGT reaches the limit value, the tube has to be plugged [4,5,6]. Many outages of nuclear power plant units caused by severe wear between AVBs and SGTs have been reported. The influence of the AVB on wear behavior has attracted many researchers’ attention
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