STP611

    Annealing of Irradiation Damage in High-Copper Ferritic Steels

    Published: Jan 1976


      Format Pages Price  
    PDF (308K) 15 $25   ADD TO CART
    Complete Source PDF (9.5M) 15 $126   ADD TO CART


    Abstract

    The postirradiation annealing response of one SA 302 Grade B plate material and two high-copper weld metals irradiated at 550 °F (288°C) was measured for annealing temperatures in the range 600°F (316°C) to 850 °F (454°C) and annealing times up to 1 week (168 h). Recovery of pre-irradiation microhardness was followed for all three steels. In addition, recovery of ductile-brittle transition temperature (DBTT) was measured for the SA 302 Grade B material. Optical and transmission electron microscopy (TEM) were utilized to characterize the microstructures of the irradiated and annealed SA 302 Grade B plate material. Small fracture specimens of all three steels were broken in an Auger spectrometer. Auger analyses were performed on the fracture surfaces, which were subsequently characterized with scanning electron microscopy (SEM). Microhardness measurements indicated that the weld metal with the highest copper content (0.31 weight percent) and lowest fluence (5.7 × 1018 neutrons (n)/cm2) was the most resistant to softening under postirradiation annealing. The recovery of ductility as measured by the DBTT shift of the SA 302 Grade B material paralleled the recovery as measured by microhardness. All three steels showed increased recovery with higher annealing temperatures and longer annealing times. No visible microstructural changes accompanied irradiation or annealing. Some evidence for a 5 to 10 percent increase in copper concentration at the fracture surfaces of irradiated specimens was obtained. No significant segregation of any element to the fracture surfaces, however, was observed to result from irradiation or postirradiation annealing. The measured annealing response of these steels agreed well with the values predicted by a previously developed theoretical model based on the dissolution of copper-vacancy aggregates.

    Keywords:

    radiation, neutron irradiation, radiation effects, microhardness, ductility, microstructure, solute-vacancy clusters, ferritic steels, annealing, recovery, model, theory, Auger spectrometry, segregation, precipitation


    Author Information:

    Spitznagel, JA
    Senior engineers, Westinghouse Research Laboratories, Pittsburgh, Pa.

    Shogan, RP
    Senior engineers, Westinghouse Research Laboratories, Pittsburgh, Pa.

    Phillips, JH
    Engineer, Westinghouse Pressurized Water Reactors, Systems Division, Pittsburgh, Pa.


    Paper ID: STP38064S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP38064S


    CrossRef ASTM International is a member of CrossRef.