An Experimental Study of the Plate-Nozzle Tensile Test for Cracked Reactor Vessel Nozzles.

摘要

A series of four frozen stress photoelastic tests was conducted in order to assess the validity of finite element models of tensilely loaded plates containing cracked reactor vessel nozzle geometries. Although the number of tests was so small as to limit the validity of conclusions to conjecture,the authors feel that the stiffness derivative program yields reasonably accurate SIF distribution predictions along the flaw borders studied,but the flaw shapes do not reflect the flattening obtained experimentally near the center of the flaw border. This causes the flaw depths to vary and,for certain ranges of a/T,may result in a shift of the SIF versus flaw position curve.