The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels

• Published in: Journal of nuclear materials Vol. 356; no. 1; pp. 62 - 69
• Main Authors: Maloy, Stuart A., Toloczko, M.B., McClellan, K.J., Romero, T., Kohno, Y., Garner, F.A., Kurtz, R.J., Kimura, A.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 15.09.2006; Elsevier
• Subjects: Applied sciences; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fuels; Installations for energy generation and conversion: thermal and electrical energy; Nuclear fuels; Preparation and processing of nuclear fuels; N0100; S0800; R0300; Ferritic martensitic steel; Hardening; Chromium alloy; Temperature effect; Fast reactor; Silicon; Comparative study; Strength; Nuclear reactor
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2006.05.024

Tensile testing has been performed at 25 and at ∼400 °C on two ferritic/martensitic steels (JFMS and HT-9) after irradiation in FFTF to up to ∼70 dpa at 373–433 °C. As observed in previous studies, this range of irradiation temperatures has a significant effect on hardening. The percent increase in yield stress decreases with increasing irradiation temperature from 373 to 433 °C. The JFMS alloy, which has 0.7 wt% silicon, exhibits approximately a factor of two increase in yield strength between tests at 427 and at 373 °C, and shows an increase in hardening with increasing dose. A comparison of the JFMS tensile properties to the properties of other ferritic/martensitic steels suggests that this hardening is due to precipitation of a Si-rich laves phase in this alloy. The HT-9 alloy, which contains more chromium and more carbon but less silicon (0.2 wt%), less molybdenum and less nickel, hardens during irradiation at 373 °C, but shows less hardening for irradiations performed at 427 °C and no increase in yield stress with increasing dose beyond 10 dpa.