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Volume 36 Issue 6
Feb.  2025
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ZHENG Liangang, XIE Hai, SU Dongchuan, SHAO Xuejiao. Study of Reactor Pressure Vessel Fatigue Crack Growth Analysis Based on ANSYS[J]. Nuclear Power Engineering, 2015, 36(6): 67-69. doi: 10.13832/j.jnpe.2015.06.0067
Citation: ZHENG Liangang, XIE Hai, SU Dongchuan, SHAO Xuejiao. Study of Reactor Pressure Vessel Fatigue Crack Growth Analysis Based on ANSYS[J]. Nuclear Power Engineering, 2015, 36(6): 67-69. doi: 10.13832/j.jnpe.2015.06.0067

Study of Reactor Pressure Vessel Fatigue Crack Growth Analysis Based on ANSYS

doi: 10.13832/j.jnpe.2015.06.0067
  • Received Date: 2015-03-24
  • Rev Recd Date: 2015-10-12
  • Available Online: 2025-02-15
  • There are two possible methods proposed in RCC-M paragraph ZG to perform the fracture analysis. The first method is easy to carry out. But the calculation result is too conservative and difficult to satisfy the criterion of RCC-M. The second method is to perform the fatigue crack growth analysis. This method is very complex. And there is too much calculation using this method. This paper provide a fatigue crack growth program writing with ANSYS code APDL commands. Calculation of reactor pressure vessel fatigue crack growth is performed using this program.

     

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