Estimating Structural Integrity of Type 304 Stainless Steel Plates and Pipes Containing Small Defects

摘要

In recent years there has been considerable demand for accurate assessment of the influence of defects on reactor structural component integrity. Analyses used must account for the effect of large plastic deformation of low-strength ductile materials. A number of models have been developed for the analysis of reactor coolant piping as well as less ductile plate and piping, but these models have not been verified for the full spectrum of potential materials and configurations encountered in reactor components. The paper presents preliminary test program results and some evaluation of these models, specifically, the flow stress approach and the two-parameter fracture criterion (TPFC). The tests were conducted with annealed Type 304 stainless steel flat tensile specimens containing triangular, rectangular, or part-circular surface flaws, and pressurized pipe specimens with internal or external triangular surface defects. (ERA citation 04:046551)