You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    If you are an ASTM Compass Subscriber and this document is part of your subscription, you can access it for free at ASTM Compass
    STP1175

    Annealing Experiments on Irradiated NiCrMo Weld Metal

    Published: 01 January 1994


      Format Pages Price  
    PDF (192K) 11 $25   ADD TO CART
    Complete Source PDF (27M) 1304 $180   ADD TO CART

    Cite this document

    X Add email address send
    X
      .RIS For RefWorks, EndNote, ProCite, Reference Manager, Zoteo, and many others.   .DOCX For Microsoft Word


    Abstract

    Charpy-V impact, tensile, drop weight and fracture mechanics specimens from a NiCrMo weld metal with a relatively high copper content (0.27 %) were irradiated at about 315 °C to neutron fluences between 2 and 7 x 1019 cm-2 (E > 1 MeV). Post-irradiation annealing experiments on all the above mentioned types of specimens were conducted at an annealing temperature of 450 °C, which was selected after recovery experiments on hardness and impact test specimens only, performed at annealing temperatures in the range 350 – 550 °C and with annealing times of up to 168 h. Annealing at 550 °C, a temperature which is not applicable to a reactor pressure vessel (RPV) in situ, yielded impact properties better than the pre-irradiation values. After annealing at 450 °C, which can be applied in annealing of RPVs, residual shifts of transition temperature of 40 to 50 K remained. Another weldment of similar composition irradiated at about 285 °C reached the same post-anneal level of residual shift. Some specimens were re-irradiated after irradiation and subsequent 450 °C/60 h annealing. They reached the same total transition temperature shift after an additional fluence of the same magnitude as the fluence of the primary irradiation. After a second 450 °C annealing the residual shift again was about 40 K.

    Keywords:

    neutron irradiation, annealing, reactor pressure vessel, low alloy steel, weld metal, mechanical properties


    Author Information:

    Leitz, C
    Manager, deputy director and manager, Power Generation Group KWU, SIEMENS AG, Erlangen,

    Klausnitzer, EN
    Manager, deputy director and manager, Power Generation Group KWU, SIEMENS AG, Erlangen,

    Hofmann, G
    Manager, deputy director and manager, Power Generation Group KWU, SIEMENS AG, Erlangen,


    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP23946S