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

J. Y. Jeon, J. S. Kim, Yun-Jae Kim, J. W. Kim, J. S. Kim

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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
Title of host publicationProcedia Engineering
PublisherElsevier Ltd
Pages1564-1571
Number of pages8
Volume130
DOIs
Publication statusPublished - 2015
Event14th International Conference on Pressure Vessel Technology, 2015 - Shanghai, China
Duration: 2015 Sep 232015 Sep 26

Other

Other14th International Conference on Pressure Vessel Technology, 2015
CountryChina
CityShanghai
Period15/9/2315/9/26

Fingerprint

Steam generators
Bearing capacity
Numerical analysis
Loads (forces)
Acoustic waves
Ductile fracture
Nuclear power plants
Crack propagation
Mechanics
Finite element method

Keywords

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

ASJC Scopus subject areas

  • Engineering(all)

Cite this

Jeon, J. Y., Kim, J. S., Kim, Y-J., Kim, J. W., & Kim, J. S. (2015). Numerical Analysis to Predict Load-Bearing Capacity of Flawed Steam Generator Tubes in Nuclear Plants. In Procedia Engineering (Vol. 130, pp. 1564-1571). Elsevier Ltd. https://doi.org/10.1016/j.proeng.2015.12.326

Numerical Analysis to Predict Load-Bearing Capacity of Flawed Steam Generator Tubes in Nuclear Plants. / Jeon, J. Y.; Kim, J. S.; Kim, Yun-Jae; Kim, J. W.; Kim, J. S.

Procedia Engineering. Vol. 130 Elsevier Ltd, 2015. p. 1564-1571.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Jeon, JY, Kim, JS, Kim, Y-J, Kim, JW & Kim, JS 2015, Numerical Analysis to Predict Load-Bearing Capacity of Flawed Steam Generator Tubes in Nuclear Plants. in Procedia Engineering. vol. 130, Elsevier Ltd, pp. 1564-1571, 14th International Conference on Pressure Vessel Technology, 2015, Shanghai, China, 15/9/23. https://doi.org/10.1016/j.proeng.2015.12.326
Jeon JY, Kim JS, Kim Y-J, Kim JW, Kim JS. Numerical Analysis to Predict Load-Bearing Capacity of Flawed Steam Generator Tubes in Nuclear Plants. In Procedia Engineering. Vol. 130. Elsevier Ltd. 2015. p. 1564-1571 https://doi.org/10.1016/j.proeng.2015.12.326
Jeon, J. Y. ; Kim, J. S. ; Kim, Yun-Jae ; Kim, J. W. ; Kim, J. S. / Numerical Analysis to Predict Load-Bearing Capacity of Flawed Steam Generator Tubes in Nuclear Plants. Procedia Engineering. Vol. 130 Elsevier Ltd, 2015. pp. 1564-1571
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