Predictions of structural integrity of steam generator tubes under normal operating, accident, and severe accident conditions

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Available models for predicting failure of flawed and unflawed steam generator tubes under normal operating, accident, and severe accident conditions are reviewed. Tests conducted in the past, though limited, tended to show that the earlier flow-stress model for part-through-wall axial cracks overestimated the damaging influence of deep cracks. This observation is confirmed by further tests at high temperatures as well as by finite element analysis. A modified correlation for deep cracks can correct this shortcoming of the model. Recent tests have shown that lateral restraint can significantly increase the failure pressure of tubes with unsymmetrical circumferential cracks. This observation is ... continued below

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18 p.

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Majumdar, S. September 1, 1996.

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Description

Available models for predicting failure of flawed and unflawed steam generator tubes under normal operating, accident, and severe accident conditions are reviewed. Tests conducted in the past, though limited, tended to show that the earlier flow-stress model for part-through-wall axial cracks overestimated the damaging influence of deep cracks. This observation is confirmed by further tests at high temperatures as well as by finite element analysis. A modified correlation for deep cracks can correct this shortcoming of the model. Recent tests have shown that lateral restraint can significantly increase the failure pressure of tubes with unsymmetrical circumferential cracks. This observation is confirmed by finite element analysis. The rate-independent flow stress models that are successful at low temperatures cannot predict the rate sensitive failure behavior of steam generator tubes at high temperatures. Therefore, a creep rupture model for predicting failure is developed and validated by tests under varying temperature and pressure loading expected during severe accidents.

Physical Description

18 p.

Notes

INIS; OSTI as DE97053457

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  • 24. water reactor safety information meeting, Bethesda, MD (United States), 21-23 Oct 1996

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  • Other: DE97053457
  • Report No.: ANL/ET/CP--91233
  • Report No.: CONF-9610202--
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 544713
  • Archival Resource Key: ark:/67531/metadc699240

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  • September 1, 1996

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 7, 2016, 8:29 p.m.

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Majumdar, S. Predictions of structural integrity of steam generator tubes under normal operating, accident, and severe accident conditions, article, September 1, 1996; Illinois. (digital.library.unt.edu/ark:/67531/metadc699240/: accessed August 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.