STP725

    Fracture Resistance of HT-9 After Irradiation at Elevated Temperature

    Published: Jan 1981


      Format Pages Price  
    PDF (460K) 16 $25   ADD TO CART
    Complete Source PDF (13M) 16 $66   ADD TO CART


    Abstract

    HT-9, a 12 percent chromium martensitic stainless steel of interest for use in ducts for fast reactors and as a first-wall material in magnetic fusion reactors, was irradiated in the experimental breeder reactor II to obtain the first evaluation of fracture toughness changes produced by high-temperature/high-fluence irradiation in this class of alloy.

    Charpy V-notch, precracked Charpy, and tension specimens were used to evaluate the tensile and fracture behavior of this steel in the as-received condition, after 5000 h of aging at 427 and 538°C and after irradiation to a fluence of 1.1 × 1022 neutron/cm2 (E > 0.1 MeV) at 419°C in flowing sodium. The results show some tendency toward temper embrittlement at 538°C and a 108 deg C shift in the ductile-to-brittle transition after irradiation at 419°C. Charpy-V energies on the upper shelf are also depressed by the irradiation but maintain adequate levels for the applications intended. Possible mechanisms for the observed response are discussed.

    Keywords:

    breeder reactor materials, magnetic fusion reactor materials, martensitic stainless steel, irradiation embrittlement


    Author Information:

    Smidt, FA
    Supervisory metallurgist and research metallurgists, Naval Research LaboratoryTracor, Inc., WashingtonRockville, D.C.Md.

    Hawthorne, JR
    Supervisory metallurgist and research metallurgists, Naval Research LaboratoryTracor, Inc., WashingtonRockville, D.C.Md.

    Provenzano, V
    Supervisory metallurgist and research metallurgists, Naval Research LaboratoryTracor, Inc., WashingtonRockville, D.C.Md.


    Paper ID: STP28219S

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP28219S


    CrossRef ASTM International is a member of CrossRef.