Paper Title:
Fatigue Crack Growth Behaviors of AISI Type 347 Nuclear Piping Material
  Abstract

The effect of the temperature and microstructure on the fatigue crack growth behaviors of two microstucturally different AISI type 347 stainless steel(SS)s are studied at reactor operating temperature conditions. From the results, it was observed that the fatigue crack growth rate(FCGR) of type 347 SS increased as the test temperature was increased. However, its temperature sensitivity was reduced when the ΔK was large. The measured FCGRs for both TP347-LP and TP347-HP at 25oC and 345oC were lower than those presented in the ASME code. Especially near the threshold region, the trend curve in ASME code overestimated the FCGR of type 347 SS when compared with the obtained data. Even though the effect of the microstructure on the macro-crack growth rate was not significant during stage 2, the differences between threshold values for the specimen with a high precipitate density and the one with a low precipitate density were observed. It is assumed that these differences in the precipitate density, which resulted in a difference in mean free path length of dislocation movement, are the source of the difference in ΔKth of type 347 steels.

  Info
Periodical
Advanced Materials Research (Volumes 26-28)
Edited by
Young Won Chang, Nack J. Kim and Chong Soo Lee
Pages
1129-1132
DOI
10.4028/www.scientific.net/AMR.26-28.1129
Citation
J. H. Yoon, J. M. Lee, M. W. Kim, B. S. Lee, "Fatigue Crack Growth Behaviors of AISI Type 347 Nuclear Piping Material", Advanced Materials Research, Vols. 26-28, pp. 1129-1132, 2007
Online since
October 2007
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Price
$32.00
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