Tensile behaviour of 9Cr–1Mo tempered martensitic steels irradiated up to 20 dpa in a spallation environment - Archive ouverte HAL Access content directly
Journal Articles Journal of Nuclear Materials Year : 2008

Tensile behaviour of 9Cr–1Mo tempered martensitic steels irradiated up to 20 dpa in a spallation environment

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Abstract

Tensile specimens of 9Cr–1Mo (EM10) and mod 9Cr–1Mo (T91) martensitic steels in the normalized and tempered metallurgical conditions were irradiated with high energy protons and neutrons up to 20 dpa at average temperatures up to about 360 °C. Tensile tests were carried out at room temperature and 250 °C and a few samples were tested at 350 °C. The fracture surfaces of selected specimens were characterized by Scanning Electron Microscopy (SEM). While all irradiated specimens displayed at room temperature considerable hardening and loss of ductility, those irradiated to doses above approximately 16 dpa exhibited a fully brittle behaviour and the SEM observations revealed significant amounts of intergranular fracture. Helium accumulation, up to about 0.18 at.% in the specimens irradiated to 20 dpa, is believed to be one of the main factors which triggered the brittle behaviour and intergranular fracture mode. One EM10 and one T91 specimen irradiated to 20 dpa were annealed at 700 °C for 1 h following irradiation and subsequently tensile tested. In both cases, a remarkable recovery of ductility and strain-hardening capacity was observed after annealing, while the strength remained significantly above that of the unirradiated material.
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cea-02355774 , version 1 (04-10-2022)

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Attribution - CC BY 4.0

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J. Henry, X. Averty, Y. Dai, J. P. Pizzanelli. Tensile behaviour of 9Cr–1Mo tempered martensitic steels irradiated up to 20 dpa in a spallation environment. Journal of Nuclear Materials, 2008, 377 (1), pp.80-93. ⟨10.1016/j.jnucmat.2008.02.027⟩. ⟨cea-02355774⟩

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