Mechanical and microstructural analysis of an EM10 wrapper tube after neutron irradiation in Phenix

JOURNAL OF NUCLEAR MATERIALS

卷:543

Article

Tissot, O.¹  Gavoille, P.²  Verhaeghe, B.²  Henry, J.¹ 

[1] Univ Paris Saclay, CEA, Serv Rech Met, Appl, F-91191 Gif Sur Yvette, France

[2] Univ Paris Saclay, CEA, Serv Etud Mat Irradies, F-91191 Gif Sur Yvette, France

关键词: Ferritic/Martensitic;    Neutron irradiation;    EM10;    Hexagonal duct;    Mechanical tests;    Microstructural characterization;   

DOI  :  10.1016/j.jnucmat.2020.152575

来源: Elsevier

【 摘 要 】

The 9Cr-1Mo tempered martensitic steel was irradiated with fast neutrons in the French Phenix reactor. Mechanical tests, density measurement as well as microstructural investigations were carried out following irradiation up to 155 dpa in the temperature range 386 degrees C - 525 degrees C. Tensile, elongation and impact properties were only slightly modified by irradiation. Microstructural investigations revealed the presence of cavities, however the resulting swelling was low (0.1%). In most cases, the dislocation microstructure was arranged in a network. Nevertheless, some large loops were observed after irradiation at 398 degrees C to 112 dpa. Overall, the EM10 steel showed excellent radiation resistance, which confirmed that this steel is an attractive wrapper candidate material for future sodium-cooled GEN IV fast reactors. (C) 2020 Elsevier B.V. All rights reserved.

【 授权许可】

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