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Volume 43 Issue 2
Apr.  2022
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Zhang Jianxin, Gu Jipin, Chen Shuming, Pu Enshan, Guo Xiaoxian, Li Hailiang, Fang Jinghui. Fatigue Reliability Test and Evaluation of Main Pump Spindle of Nuclear Power Plant Reactor[J]. Nuclear Power Engineering, 2022, 43(2): 219-225. doi: 10.13832/j.jnpe.2022.02.0219
Citation: Zhang Jianxin, Gu Jipin, Chen Shuming, Pu Enshan, Guo Xiaoxian, Li Hailiang, Fang Jinghui. Fatigue Reliability Test and Evaluation of Main Pump Spindle of Nuclear Power Plant Reactor[J]. Nuclear Power Engineering, 2022, 43(2): 219-225. doi: 10.13832/j.jnpe.2022.02.0219

Fatigue Reliability Test and Evaluation of Main Pump Spindle of Nuclear Power Plant Reactor

doi: 10.13832/j.jnpe.2022.02.0219
  • Received Date: 2021-03-10
  • Rev Recd Date: 2021-03-22
  • Publish Date: 2022-04-02
  • In order to obtain the fatigue reliability data of the main spindle material of the nuclear power plant reactor under a given confidence level and different reliability levels, a simulation spindle with the same inner and outer diameter dimensions and processing technology as the product spindle was manufactured for sampling. The fatigue lives of six kinds of specimens including room temperature smooth, room temperature weld, room temperature notch, high temperature smooth, high temperature weld and high temperature notch were tested. The lower confidence limit equation of the fatigue reliability life with different reliability levels and the reliability fatigue limit of the six kinds of specimens were determined by reliability statistical methods when the confidence level was 0.9 or 0.95. The differences and revised methods between the fatigue life of the specimens and the spindle were analyzed. Using the revised specimen data, the reliability assessment of the spindle fatigue failure weak links were carried out. The results show that the reliability of the spindle without fatigue failure during the lifetime exceeds 0.9999 when the confidence level is 0.9 or 0.95. In this paper, a more accurate reliability assessment of spindle fatigue failure of reactor main pump is achieved.

     

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