Fatigue response and life prediction of selected reactor materials

Research output: Contribution to journalConference articlepeer-review

Abstract

This paper analyzes experimental fatigue response for selected unirradiated and irradiated reactor materials: AISI 316 stainless steel, ferritic/martensitic MANET and HT9 steels. Available tensile test results on the same or similar materials are used to predict changes in fatigue response using the Universal Slopes method. The predictions are compared with the experimental data to assess the potential for using tensile data to predict reactor component fatigue response. It was found that the effect of irradiation on fatigue life was less severe than on tensile properties. However, tensile properties are useful for qualitative predictions of fatigue response.

Original languageEnglish (US)
Pages (from-to)502-515
Number of pages14
JournalASTM Special Technical Publication
Issue number1447
DOIs
StatePublished - Jan 1 2004
EventEffects of Radiation on Materials: 21st International Symposium - Tucson, AZ, United States
Duration: Jun 18 2002Jun 20 2002

Keywords

  • Austenitic stainless steel
  • Fatigue life prediction
  • Fatigue response
  • Ferritic/martensitic steel
  • Radiation exposure
  • Tensile properties
  • Universal Slopes

ASJC Scopus subject areas

  • Engineering(all)

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