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Volume 42 Issue S2
Dec.  2021
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Shi Kaikai, Zheng Bin, Zheng Liangang. Simulation Study on Fatigue Growth of Semi-Circular Axial Crack on Inner Surface of Core Barrel under Transient Loads[J]. Nuclear Power Engineering, 2021, 42(S2): 1-4. doi: 10.13832/j.jnpe.2021.S2.0001
Citation: Shi Kaikai, Zheng Bin, Zheng Liangang. Simulation Study on Fatigue Growth of Semi-Circular Axial Crack on Inner Surface of Core Barrel under Transient Loads[J]. Nuclear Power Engineering, 2021, 42(S2): 1-4. doi: 10.13832/j.jnpe.2021.S2.0001

Simulation Study on Fatigue Growth of Semi-Circular Axial Crack on Inner Surface of Core Barrel under Transient Loads

doi: 10.13832/j.jnpe.2021.S2.0001
  • Received Date: 2021-07-19
  • Accepted Date: 2021-12-06
  • Rev Recd Date: 2021-08-05
  • Publish Date: 2021-12-29
  • In order to study the fatigue growth of inner surface cracks in the core barrel under transient loads, the change law of crack morphology of semi-circular axial crack (crack depth d is 10 mm and crack surface length L is 20 mm) on the inner surface of reactor pressure vessel core barrel under transient load is simulated by using the crack block analysis method in the Zencrack software, wherein, the fatigue crack growth rate model of core cylinder material is realized by subprogram. Through the simulation study, it is known that the subprogram realization of material fatigue crack growth rate model is an efficient way to analyze the simulation of crack fatigue growth; the stress intensity factor calculated by the crack block analysis method is similar to that calculated by the standard engineering analysis method;. For the axial cracks with a semi-circular initial state on the inner surface of the core barrel, the initial crack ovalization will occur during the fatigue growth of the crack under transient loads.

     

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