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Volume 42 Issue 4
Aug.  2021
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Su Dongchuan, Xie Hai, Zhang Yixiong, Cui Huaiming, Wu Lin. Study on Fast Fracture Evaluation Method for Reactor Pressure Vessel with Excessive Carbon Content[J]. Nuclear Power Engineering, 2021, 42(4): 282-288. doi: 10.13832/j.jnpe.2021.04.0282
Citation: Su Dongchuan, Xie Hai, Zhang Yixiong, Cui Huaiming, Wu Lin. Study on Fast Fracture Evaluation Method for Reactor Pressure Vessel with Excessive Carbon Content[J]. Nuclear Power Engineering, 2021, 42(4): 282-288. doi: 10.13832/j.jnpe.2021.04.0282

Study on Fast Fracture Evaluation Method for Reactor Pressure Vessel with Excessive Carbon Content

doi: 10.13832/j.jnpe.2021.04.0282
  • Received Date: 2021-04-06
  • Rev Recd Date: 2021-04-14
  • Publish Date: 2021-08-15
  • The initial non-ductile transition temperature is an important input parameter in fast fracture evaluation according to the RCC-M code. The initial non-ductile transition temperature (RTNDT) will be affected by the carbon content, but there is no quantitative relationship between them. When the carbon content of the reactor pressure vessel exceeds the standard, it is necessary to complete the fast fracture evaluation without quantitative relationship to ensure the integrality of RPV. In this paper, the evaluation method of the fast fracture of RPV with excessive carbon content is studied. Taking the RPV core barrel with excessive carbon content as an example, the defect repair is considered, and the fast fracture analysis and evaluation are carried out by calculating the maximum initial non-ductile transition temperature. This method can support the operation and the in-service inspection of the pressure vessels with excessive carbon content.

     

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