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

Abstract : TENSILE BEHAVIOUR OF 9Cr MARTENSITIC STEELS IRRADIATED UP TO 20 DPA IN A SPALLATION ENVIRONMENTJ. Henry1), X. Averty1), Y. Dai1), J-P. Pizzanelli1)1) Commissariat a L-Energie Atomique, CEA-Saclay, DEN-DMN 91191 Gif-sur-Yvette, France2) Paul Scherrer Institut, CH-5232 Villigen PSI, SwitzerlandTensile samples of 9Cr 1Mo (EM10) and mod 9Cr 1Mo (T91) martensitic steels were irradiated in the SINQ target (STIP 2 irradiation) to a maximum dose of 20 dpa with the mean irradiation temperature ranging from about 115DC to 350DC. For EM 10, two geometries were used for the tensile samples, the S (gauge section dimensions were 5 mm long, 1 mm wide, 0.4 mm thick) and L (5 mm long, 1.5 mm wide and 0.75 mm thick) geometries while for T91 only S type specimens were irradiated. Tensile tests were conducted at Room Temperature (RT) and at 250DC and for a few samples at 350DC.At RT, both EM10 and T91 samples showed considerable hardening and loss of ductility as classically observed for martensitic steels irradiated below 350DC. Moreover, above about 15 dpa, the samples exhibited a total loss of ductility and some specimens irradiated to 19-20 dpa broke in the elastic regime. Likewise, in the case of the two samples tested at 350DC and which had been irradiated to the maximum dose, almost no plastic deformation was measured. For the specimens tested at 250DC such a drastic embrittlement was not observed, however the maximum exposure of the specimens tested at this temperature was about 16 dpa. In addition, one EM10 and one T91 specimen irradiated to 20 dpa were annealed for 1h at 750DC before being tested at RT. Following the heat treatment both materials regained significant uniform elongation while still exhibiting a large increase in yield stress compared to the unirradiated materials.
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J. Henry, X. Averty, Y. Dai, Jp. Pizzanelli. Tensile behaviour of 9Cr martensitic steels irradiated up to 20 dpa in a spallation environment. Journal of Nuclear Materials, Elsevier, 2008, 377. ⟨cea-02355774⟩



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