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Microstructure and Mechanical Properties of n-Irradiated Fe-Cr Model Alloys

Published online by Cambridge University Press:  26 February 2011

Milena Matijasevic  and
Abderrahim Al Mazouzi
Milena Matijasevic
Affiliation:
mmatijas@sckcen.be, SCK.CEN, reactor Materials Research, LHMA, Boeretang 200, Mol, 2400, Belgium
Abderrahim Al Mazouzi
Affiliation:
aalmazou@sckcen.be, SCK.CEN, Reactor Materials Research, LHMA, Boeretang 200, Mol, 2400, Belgium
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Abstract

High chromium ( 9-12 wt %) ferritic/martensitic steels are candidate structural materials for future fusion reactors and other advanced systems such as accelerator driven systems ADS). Their use for these applications requires a careful assessment of their mechanical stability under high energy neutron irradiation and in aggressive environments. In particular, the Cr concentration has been shown to be a key parameter to be optimized in order to guarantee the best corrosion and swelling resistance, together with the least embrittlement.

In this work, the characterization of the neutron irradiated Fe-Cr model alloys with different Cr % with respect to microstructure and mechanical tests will be presented. The behavior of Fe-Cr alloys have been studied using tensile tests at different temperature range ( from -160°C to 300°C). Irradiation-induced microstructure changes have been studied by TEM for two different irradiation doses at 300°. The density and the size distribution of the defects induced have been determined. The tensile test results indicate that Cr content affects the hardening behavior of Fe-Cr binary alloys. Hardening mechanisms are discussed in terms of Orowan type of approach by correlating TEM data to the measured irradiation hardening.

Keywords

microstructureneutron irradiationstrength
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 981: Symposium JJ – Structural and Refractory Materials for Fusion and Fission Technologies , 2006 , 0981-JJ07-06
Copyright
Copyright © Materials Research Society 2007

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References

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