Numerical Analysis to Predict Load-Bearing Capacity of Flawed Steam Generator Tubes in Nuclear Plants

J. Y. Jeon, J. S. Kim, Y. J. Kim, J. W. Kim, J. S. Kim

Research output: Contribution to journalConference articlepeer-review


This paper presents a prediction of load-bearing capacity of flawed steam generator tube using numerical analysis. Alloy 690TT steam generator tube with diameter of 19.05 mm and thickness of 1.07 mm widely used in nuclear power plants is considered in this study. Sound tubes and through-wall cracked tubes are used in tensile tests. Finite element analysis applying a damage mechanics is performed to predict ductile fracture and load-bearing capacity of the cracked tube. A strain-based fracture model is determined and applied to calculate ductile damage during the simulations. The sound tube and through-wall cracked tube tensile tests are analyzed to determine the fracture model as well as proper element size for Alloy 690TT. Crack growths are simulated by implementing stress reduction technique for failed finite element. Predicted maximum load-bearing capacity are compared with published test data.

Original languageEnglish
Pages (from-to)1564-1571
Number of pages8
JournalProcedia Engineering
Publication statusPublished - 2015
Externally publishedYes
Event14th International Conference on Pressure Vessel Technology, 2015 - Shanghai, China
Duration: 2015 Sept 232015 Sept 26


  • axial surface flaw
  • finite element analysis
  • load-bearing capacity
  • steam generator tube

ASJC Scopus subject areas

  • Building and Construction
  • General Engineering


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