STP681

    Tube-Burst Response of Irradiated Zircaloy Spent-Fuel Cladding

    Published: Jan 1979


      Format Pages Price  
    PDF (188K) 12 $25   ADD TO CART
    Complete Source PDF (11M) 12 $192   ADD TO CART


    Abstract

    Transient-heating tube-burst tests were conducted on a 50.8-cm length of Zircaloy cladding obtained from spent-fuel rods irradiated in the H. B. Robinson power reactor to a peak burn-up of 30 MWD/kg. Internal electrical resistance heaters were used to achieve nominal heating rates of 28°C/s for the tests. The tests were conducted in steam and the independent experimental variable was the initial level of helium pressurization.

    Tube burst pressures varied from 0.965 to 12.514 MPa. Corresponding burst stresses and temperatures varied from 7.5 MPa and 1135°C to 99.1 MPa and 734°C, respectively. Failure strains ranged up to 46 percent when burst occurred at upper (α + β) and β-phase temperatures and up to 30 percent for failures occurring at lower temperatures.

    No significant difference in burst behavior between unirradiated and spent nuclear fuel Zircaloy cladding was observed experimentally. No influence of axial restraint on burst strains was noted.

    Keywords:

    zirconium, zirconium alloys, irradiation, nuclear fuel cladding, tubes, burst tests, stresses, strains


    Author Information:

    Bauer, AA
    Research leader, research scientist, and research scientist, Battelle's Columbus Laboratories, Columbus, Ohio

    Lowry, LM
    Research leader, research scientist, and research scientist, Battelle's Columbus Laboratories, Columbus, Ohio

    Gallagher, WJ
    Research leader, research scientist, and research scientist, Battelle's Columbus Laboratories, Columbus, Ohio


    Paper ID: STP36696S

    Committee/Subcommittee: B10.02

    DOI: 10.1520/STP36696S


    CrossRef ASTM International is a member of CrossRef.