Low Cycle Fatigue Behavior of VVER-440 Reactor Pressure Vessel Steels at Isothermal Condition

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The fatigue life of the structural materials 15H2MFA and 08H18N10T of VVER-440 reactor pressure vessel under completely reserved total strain controlled tests were investigated. The measurements were carried out with isothermal condition at 260°C on GLEEBLE 3800 servo-hydraulic thermal mechanical simulator. The isothermal low cycle fatigue results were evaluated with the plastic strain based Coffin-Manson law, and plastic strain energy based model as well. It was shown that both methods are able to predict the fatigue life of reactor pressure vessel steels accurately.

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47-52

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February 2015

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© 2015 Trans Tech Publications Ltd. All Rights Reserved

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[1] L. F. Coffin, Fatigue at high temperature – Prediction and interpretation. Proc. Instn. Mech. Engrs. 188 (1974) 109-127.

Google Scholar

[2] M.D. Callaghan, S.R. Humphries, M. Law, M. Ho, P. Bendeich, H. Li, W.Y. Yeung: Energy-based approach for the evaluation of low cycle fatigue behaviour of 2. 25Cr–1Mo steel at elevated temperature. Materials Science and Engineering A 527 (2010).

DOI: 10.1016/j.msea.2010.05.011

Google Scholar

[3] Mageshwaran Ramesh, Hans J. Leber, Markus Diener, Ralph Spolenak, Conducting thermomechanical fatigue test in air at light water reactor relevant temperature intervals. Journal of Nuclear Materials 415 (2011) 23–30.

DOI: 10.1016/j.jnucmat.2011.05.025

Google Scholar