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


    Fatigue Crack Growth of Low-Fluence Neutron-Irradiated Stainless Steel DIN 1.4948


      Format Pages Price  
    PDF (288K) 15 $25   ADD TO CART
    Complete Source PDF (19M) 1219 $77   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


    Compact-tension (CT) specimens of stainless steel DIN 1.4948, which is similar to AISI Type 304, have been irradiated up to a fluence level of 2.1024 n.m.−2 (E > 0.1 MeV) at temperatures ranging from 330 to 823 K. Post-irradiation constant-load-amplitude crack propagation (fcp) tests were performed in air at temperatures from 298 to 823 K with frequencies ranging from 10−3 to 10 Hz and R-ratios (min. load/max. load) of 0.05 and 0.30. Irradiation hardening after the low temperature irradiations (573 K and below) caused a reduction of the fatigue crack growth rate. Irradiation at the higher temperatures did not affect the fcp at the high frequency of 10 Hz. At 823 K the combination of high R-ratio and low frequency (10−2 Hz) resulted in an increase of the post-irradiation crack growth rate with a factor 10. This irradiation effect is attributed to the observed intergranular crack propagation.


    radiation, neutron irradiation, fatigue, crack propagation, stainless steel, elevated temperature

    Author Information:

    de Vries, MI
    Research Scientist, Netherlands Energy Research Foundation, ECN, Petten (NH),

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP34375S