Fatigue Response and Life Prediction of Selected Reactor Materials

M Li; JF Stubbins

doi:10.1520/STP11252S

SYMPOSIA PAPER Published: 01 January 2004

STP11252S

Fatigue Response and Life Prediction of Selected Reactor Materials

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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.

Author Information

Li, M

Oak Ridge National Laboratory, Oak Ridge, TN

Stubbins, JF

University of Illinois at Urbana-Champaign, 214 Nuclear Engineering Laboratory, Urbana, IL

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Details

Developed by Committee: E10

Pages: 502–515

DOI: 10.1520/STP11252S

ISBN-EB: 978-0-8031-5494-0

ISBN-13: 978-0-8031-3477-5

Fatigue Response and Life Prediction of Selected Reactor Materials

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