STP956

    Analysis of the In-Reactor Creep and Rupture Life Behavior of Stabilized Austenitic Stainless Steels and the Nickel-Base Alloy Hastelloy-X

    Published: Jan 1987


      Format Pages Price  
    PDF Version (416K) 24 $25   ADD TO CART
    Complete Source PDF (14M) 24 $114   ADD TO CART


    Abstract

    An overall evaluation of several in-reactor creep and creep-rupture experiments in BR2 and FFTF on pressurized tubes of the stabilized austenitic stainless steels 1.4970, 1.4981, 1.4988 and the Ni-base alloy Hastelloy-X is given in this report. Even at temperatures around and above 0.5 Tm the analysis of the data implies that for low stress levels the stress-induced preferred absorption (SIPA) creep process is the predominant deformation mechanism. The results show that the in-reactor rupture lives of the austenitic steels as well as the Ni-base alloy Hastelloy-X are reduced compared with the rupture lives of the corresponding material in the unirradiated and post-irradiation tested conditions, so that an additional damage mechanism via helium has to be assumed to account for the reduction in rupture life.

    Analytical models have been developed, which accounts for the critical variables stress, temperature, and dpa rate and which describes in a more general way the in-reactor creep and creep-rupture life behavior of the materials mentioned above. The analysis of the results indicates clearly that the use of the unirradiated and post-irradiation data for predicting in-reactor creep and failures is invalid for these materials.

    Keywords:

    in-pile creep, elastodiffusion, in-pile creep rupture, SIPA mechanisms, temperature dependencies, activation energies, dpa rate dependency, stress dependency, dynamic resolution, helium-bubble growth


    Author Information:

    Wassilew, C
    Research scientist and division leader, Kernforschungszentrum, Karlsruhe, Karlsruhle,

    Wassilew, C., Dr-Thesis Fakultät für Maschinenbau der Universität Karlsruhe (TH), Karlsruhe,

    Ehrlich, K
    Research scientist and division leader, Kernforschungszentrum, Karlsruhe, Karlsruhle,

    Bergmann, HJ
    Research engineer, Fa. INTERATOM, Bergisch Gladbach,


    Paper ID: STP25639S

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP25639S


    CrossRef ASTM International is a member of CrossRef.