STP1245

    Irradiation Effect on Fatigue Behavior of Zircaloy-4 Cladding Tubes

    Published: Jan 1994


      Format Pages Price  
    PDF Version (184K) 10 $25   ADD TO CART
    Complete Source PDF (21M) 10 $159   ADD TO CART


    Abstract

    Since nuclear electricity has a predominant share in French generating capacity, pressurized water reactors (PWRs) are required to fit grid load following and frequency control operating conditions. Consequently, cyclic stresses appear in the fuel element cladding. In order to characterize the possible resulting clad damage, fatigue tests were performed at 350°C on unirradiated material or irradiated stress relieved Zircaloy-4 tube portions, using a special device for tube fatigue by repeated pressurization.

    It appears that, for high stress levels, the material fatigue life is not affected by irradiation. But the endurance fatigue limit undergoes a decrease from the 350 MPa value for unirradiated material to the 210 MPa value for the material irradiated for four cycles in a PWR. However, this effect seems to saturate with irradiation dose: no difference could be detected between the two cycles' results and the corresponding four cycles' results. The corrosion effect and the load following influence were also investigated: they do not appear to modify the fatigue behavior in our experimental conditions.

    Keywords:

    zirconium, zirconium alloys, fatigue behavior, cladding tubes, irradiation effects, repeated pressurization, power cycling effects, nuclear materials, nuclear applications, radiation effects


    Author Information:

    Soniak, A
    Research engineer, manager of materials studies, and laboratory head, Commissariat à l'Energie Atomique, Centre d'Etudes de Saclay, Gif-sur-Yvette,

    Lansiart, S
    Research engineer, manager of materials studies, and laboratory head, Commissariat à l'Energie Atomique, Centre d'Etudes de Saclay, Gif-sur-Yvette,

    Royer, J
    Research engineer, manager of materials studies, and laboratory head, Commissariat à l'Energie Atomique, Centre d'Etudes de Saclay, Gif-sur-Yvette,

    Mardon, J-P
    Consulting engineer, Fragema, Lyon,

    Waeckel, N
    Senior engineer, Electricité de France/Septen, Villeurbanne,


    Paper ID: STP15208S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP15208S


    CrossRef ASTM International is a member of CrossRef.