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Fatigue properties of type 316LN stainless steel in air and mercury
- Source :
- Journal of Nuclear Materials. 343:134-144
- Publication Year :
- 2005
- Publisher :
- Elsevier BV, 2005.
-
Abstract
- An extensive fatigue testing program on 316LN stainless steel was recently carried out to support the design of the mercury target container for the spallation neutron source (SNS) that is currently under construction at the Oak Ridge National Laboratory in the United States. The major objective was to determine the effects of mercury on fatigue behavior. The S – N fatigue behavior of 316LN stainless steel is characterized by a family of bilinear fatigue curves which are dependent on frequency, environment, mean stress and cold work. Generally, fatigue life increases with decreasing stress and levels off in the high cycle region to an endurance limit below which the material will not fail. For fully reversed loading as well as tensile mean stress loading conditions mercury had no effect on endurance limit. However, at higher stresses a synergistic relationship between mercury and cyclic loading frequency was observed at low frequencies. As expected, fatigue life decreased with decreasing frequency, but the response was more pronounced in mercury compared with air. As a result of liquid metal embrittlement (LME), fracture surfaces of specimens tested in mercury showed widespread brittle intergranular cracking as opposed to typical transgranular cracking for specimens tested in air. For fully reversed loading (zero mean stress) the effect of mercury disappeared as frequency increased to 10 Hz. For mean stress conditions with R -ratios of 0.1 and 0.3, LME was still evident at 10 Hz, but at 700 Hz the effect of mercury had disappeared ( R = 0.1). Further, for higher R -ratios (0.5 and 0.75) fatigue curves for 10 Hz showed no environmental effect. Finally, cold working (20%) increased tensile strength and hardness, and improved fatigue resistance. Fatigue behavior at 10 and 700 Hz was similar and no environmental effect was observed.
- Subjects :
- Nuclear and High Energy Physics
Materials science
Metallurgy
chemistry.chemical_element
Intergranular corrosion
Fatigue limit
Mercury (element)
Cracking
Brittleness
Nuclear Energy and Engineering
chemistry
Liquid metal embrittlement
Ultimate tensile strength
General Materials Science
Spallation Neutron Source
Subjects
Details
- ISSN :
- 00223115
- Volume :
- 343
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........cdedfaf518a9a56bd262906c9e37bb40
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2005.03.019