STP1175: Tensile Properties of Neutron Irradiated 316Ti and 15-15Ti Steels

    Fissolo, A
    Scientist, DTA/CEREM/DTM/SRMA,

    Lévy, V
    Scientist, DTA/CEREM/DTM/SRMA,

    Séran, JL
    Scientist, DTA/CEREM/DTM/SRMA,

    Maillard, A
    Scientist, DTA/CEREM/DTM/SRMA,

    Royer, J
    Scientist, DRN/DMT/SETIC Commissariat à l'énergie atomique, Centre d'Etudes de Saclay, GIF-SUR-YVETTE,

    Rabouille, O
    Scientist, DRN/DMT/SETIC Commissariat à l'énergie atomique, Centre d'Etudes de Saclay, GIF-SUR-YVETTE,

    Pages: 18    Published: Jan 1994


    Abstract

    This paper deals with the tensile behavior of CW316Ti and CW15-15Ti Phénix fuel pin cladding. The tension tests were conducted on defueled tubes irradiated up to 115 dpa3 in the 400–640°C temperature range. Test temperature corresponds essentially to irradiation temperature. The results emphasize that, although irradiation induces a reduction of ductility, the failure always occurs with significant plastic deformation, even for the most highly irradiated cladding.

    At irradiation temperatures below 560°C, the embrittlement of both steels is correlated to the swelling and thus to the occurrence of irradiation-induced voids; in this case, the failure is transgranular. In the high irradiation temperature range, a marked difference is observed between the two steels when the tests are conducted at the irradiation temperature, since the rupture is essentially intergranular on CW316Ti and transgranular on CW15-15Ti. The tensile properties of the CW15-15Ti cladding are better than those of CW316Ti because it swells less and is less prone to creep-like embrittlement.

    Keywords:

    Austenitic steels, 316Ti, 15-15Ti, Si-modified 15-15Ti, neutron irradiation, tensile properties, fracture observations, fuel pin, fast breeder reactor


    Paper ID: STP23964S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP23964S


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