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Thermal fracture analysis for coolant circulation pumps of nuclear reactors under thermal shock loads

  • Zhen-Huan Zhou
  • , Xin-Sheng Xu
  • , Zhen-Qun Guan
  • , Yee-Tak Andrew Leung

    Research output: Journal Publications and ReviewsRGC 22 - Publication in policy or professional journal

    Abstract

    To guarantee safety operation of the nuclear reactor coolant circulation pumps, symplectic technique was used to investigate the mechanism of the key scientific problem, i.e., the fracture problem under the thermal shock. The axial symmetry transient temperature function, displacements and stresses were obtained by using a generalized symplectic approach and separation of variables. Thus, the analytical formulations of the stress intensity factors (SIF) were derived. In numerical examples, a parametric analysis was performed to study the crack behavior. For practice, a certain mainshaft of the nuclear main pump was evaluated.
    Original languageEnglish
    Pages (from-to)366-370
    Journal兵工学报
    Volume32
    Issue numberSUPPL. 2
    Publication statusPublished - Dec 2011

    Research Keywords

    • Hamilton system
    • Quasi-static analysis
    • Stress intensity factors
    • Symplectic expansion
    • Thermal shock load

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