We analyze the conditions for stable and unstable crack propagation by the ductile fracture mechanism under quasistatic loading. Numerical modeling for the crack propagation is performed by a finite-element method using a strain-based failure criterion. The influence of the ratio of the unit crack extension to the plastic zone size on the trend of J R -curves is studied. Based on these investigations, we have defined the conditions whereby a crack may propagate in an unstable manner against a background of a small-scale and general yield. A criterion for the absence of any unstable crack propagation has been formulated for the reactor pressure vessel internals made of austenitic steels and exposed to an intensive neutron irradiation.Keywords: stable and unstable crack propagation conditions, ductile fracture, strain-based failure criterion, austenitic steels.
NotationK I -stress intensity factor K c I -critical stress intensity factor D -damaging neutron dose J -Cherepanov-Rice contour integral J c -critical value of the J-integral by the crack start criterion k -Odqvist parameter (the length of the deformation path) r uc -unit crack extension size e f cr -critical strain corresponding to the crack extension by a value of r uc r p -distance between the crack tip and the plastic zone boundary along the crack extension lineIntroduction. One of the most significant operating factors that have an influence on the materials of internals of fast neutron reactors (FN) or water-moderated, water-cooled reactors (WWER) is the intensive neutron irradiation. Specifically, the intensity of the damaging neutron dose (dD dt) for some components, e.g., internals, is as high as 1 dpa/year for FN reactors, 1 dpa/year for WWER-440 reactors and 1.5-2 dpa/year for WWER-1000 reactors.The intensive irradiation has dictated the choice of materials -austenitic chromium-nickel steels -for the reactor pressure vessel (RPV) internals. For FN and WWER reactors the internals are made of steels Kh18N9 and Kh18N10T, respectively.