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


    Interaction of Strain and Radiation Damages in a Pressure Vessel Steel


      Format Pages Price  
    PDF (236K) 16 $25   ADD TO CART
    Complete Source PDF (13M) 620 $192   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


    Radiation damage in nuclear reactor pressure vessel steels is greatly affected by the initial stage of the material. Among parameters that characterize this initial stage, prestrain or strain aging play a very important role.

    A study of the interaction of strain and radiation damages was performed to indicate their linear summation rule.

    In tension tests, the large effect of prestrain has been proved; yield strength increases have been observed to be very dependent on their initial value, and a model for that dependence has been proposed.

    Irradiation embrittlement is affected by the initial prestrain for high neutron doses only (above about 1 } 1019 neutrons (n)/cm2), when effect of saturation is pronounced. Irradiation also increases the flow transition stress, but less than the yield strength increase, so that “turbulent” flow for higher neutron doses starts just above yield strength.


    radiation, neutron irradiation, neutron-beams, radiation effects, nuclear reactors, pressure vessels, steels, iron alloys, hardening (materials), embrittlement, saturation, strains, stress-strain diagrams, tension tests, impact tests, transition temperature

    Author Information:

    Brumovský, M
    Head, Fracture Mechanics Group, Škoda Works, Plzeň, Czechoslovakia

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP33675S