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

    Analysis of Radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Coordinated Research Program

    Published: 01 January 1993

      Format Pages Price  
    PDF (384K) 17 $25   ADD TO CART
    Complete Source PDF (7.9M) 399 $103   ADD TO CART

    Cite this document

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


    Test blocks of a manganese-nickel-molybdenum (Mn-Ni-Mo) low-alloy steel, machined from a nozzle cut-out of a 230-mm-thick forging shell, were provided by France in 1978 to be investigated in the second phase of an IAEA-coordinated research program on the behavior of advanced pressure vessel steels under neutron irradiation.

    The results obtained by different laboratories exhibit a great deal of scatter in Charpy-V transition temperatures, both in the initial condition and after neutron irradiation. Therefore, the shifts in Charpy-V transition curves induced by neutron irradiation at similar fluences of about 3 × 1023 n ∙ m-2 (E ⩾ 1 MeV) cover a wide temperature range from 0 up to 110°C.

    A more detailed investigation of these results was undertaken, and additional Charpy tests were conducted to clarify the considerable uncertainty about the sensitivity of this forging to radiation embrittlement. The differences in results were found to be due to the various orientations and locations of the Charpy-V specimens extracted by the different laboratories, in some cases to insufficient test data in the transition region of the Charpy curve, and to the detrimental effect on Charpy-V properties of segregated zones (ghost lines) found in specific locations of large forgings.


    neutron irradiation, radiation embrittlement, impact test, transition temperature, low-alloy steels, segregations, forgings, intergranular rupture

    Author Information:

    Soulat, PE
    Engineer, Commissariat à l'Energie Atomique, CEREM-SRMA, Centre d'Etudes Nucléaires (CEN) de Saclay, Gif-sur-Yvette,

    Houssin, B
    Senior consulting engineer, Paris-la-Défense,

    Bocquet, P
    Senior research engineer, Creusot-Loire Industrie, Centre de Recherches des Matériaux du Creusot, Le Creusot,

    Bethmont, M
    Engineer, Electricité de France, DER-Les Renardières, Moret-sur-Loing,

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP24780S