STP1270

    Swelling, Mechanical Properties and Structure of Austenitic High-Nickel Alloy Irradiated in a Fast Reactor

    Published: Jan 1996


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    Abstract

    Specimens from fuel assembly wrappers and control rod cases of 0.07C-15Cr-35Ni-3Mo-B-Zr-Y alloy were investigated after irradiation in the BOR-60 and BN-600 reactors up to a maximum damage dose of about 110 dpa at temperatures between 340 to 550°C.

    Maximum swelling occurs at 420 to 430°C with 6% at a dose of about 80 dpa and 13.5% at a dose of 108 dpa. The maximum change in strength properties and corresponding decrease of ductility occur at an irradiation temperature of 385°C. With increasing testing temperature the ductility increases from 3–6% up to 22% at 450°C for the material irradiated at 60–80 dpa.

    Frank dislocation loops with an average diameter of 25 nm (concentration is 2×1016 cm−3), voids having diameter between 20 to 23 nm (concentration is (6–7)×1014 cm−3) and semicoherent needle-like precipitates with an average length of 21 nm, oriented to several directions, were observed in the alloy structure irradiated to 60 dpa at 430°C.

    Analysis of the experimental data was performed and the service life time of the investigated alloy was estimated for use as a material for control rod cases of the BOR-60 reactor.

    Keywords:

    high-nickel alloys, mechanical properties, neutron irradiation, radiation swelling


    Author Information:

    Shamardin, VK
    Head of laboratory, Leading Research Worker, Senior Research Worker, Research Worker, Senior Research Worker, Research Institute of Atomic Reactors, Dimitrovgrad, Ulyanovsk Region

    Neustroev, VS
    Head of laboratory, Leading Research Worker, Senior Research Worker, Research Worker, Senior Research Worker, Research Institute of Atomic Reactors, Dimitrovgrad, Ulyanovsk Region

    Povstyanko, AV
    Head of laboratory, Leading Research Worker, Senior Research Worker, Research Worker, Senior Research Worker, Research Institute of Atomic Reactors, Dimitrovgrad, Ulyanovsk Region

    Bulanova, TM
    Head of laboratory, Leading Research Worker, Senior Research Worker, Research Worker, Senior Research Worker, Research Institute of Atomic Reactors, Dimitrovgrad, Ulyanovsk Region

    Ostrovsky, ZE
    Head of laboratory, Leading Research Worker, Senior Research Worker, Research Worker, Senior Research Worker, Research Institute of Atomic Reactors, Dimitrovgrad, Ulyanovsk Region

    Kuznetzov, AA
    Senior Research Worker, Senior Research Worker, Head of Laboratory, Central Research Institute of Structural Materials, St.-Petersburg,

    Kursevitch, IP
    Senior Research Worker, Senior Research Worker, Head of Laboratory, Central Research Institute of Structural Materials, St.-Petersburg,

    Nikolaev, VA
    Senior Research Worker, Senior Research Worker, Head of Laboratory, Central Research Institute of Structural Materials, St.-Petersburg,


    Paper ID: STP16512S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP16512S


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