Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Deterministic Fracture Mechanics Analysis of Pressurized Thermal Shock

  • M. J. Jhung (Korea Institute of Nuclear Safety) ;
  • Park, Y. W. (Korea Institute of Nuclear Safety)
  • Published : 1998.10.01
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Abstract

An analysis program for the evaluation of pressure vessel integrity under pressurized thermal shock (PTS) is developed. For given material properties and transient history such as temperature and pressure, the stress distribution is calculated and then stress intensity factors are obtained for a wide range of crack sizes. The stress intensity factors are compared with the fracture toughness to check if cracking is expected to occur during the transient. Using this program a round robin problem of PTS during a small break loss of coolant transient has been analyzed as a part of the international comparative assessment study. The allowable maximum reference nil-ductility transition temperatures are determined for various crack sizes.

Keywords

References

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