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

Conference · Tue Jul 01 04:00:00 EDT 2008

OSTI ID:21091573

Matijasevic, Milena; Al Mazouzi, Abderrahim ^[1]

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1. Reactor materials research, SCK-CEN, Mol (Belgium)

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 deg. C to 300 deg. C). Irradiation-induced microstructure changes have been studied by TEM for two different irradiation doses at 300 deg. C. 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. (authors)

• Research Organization: Materials Research Society, 506 Keystone Drive, Warrendale, PA, 15086-7573 (United States)
• OSTI ID: 21091573
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
BINARY ALLOY SYSTEMS
CHROMIUM ALLOYS
CORROSION
EMBRITTLEMENT
FERRITIC STEELS
HARDENING
MARTENSITIC STEELS
MECHANICAL PROPERTIES
MECHANICAL TESTS
MICROSTRUCTURE
NEUTRON BEAMS
RADIATION DOSES
SWELLING
TEMPERATURE RANGE 0400-1000 K
TRANSMISSION ELECTRON MICROSCOPY