Analysis of fracture mechanics of the reactor pressure vessel (RPV) by taking into account residual stresses. Part 2: stress analysis, assessment of integrity and experimental investigation

摘要

The main pant of fracture mechanical safety assessment is the initiation prove. The distribution of residual stress and the material properties of cladding, HAZ and base material was determined for the RPV cladding and the base material at the cylindrical shell of a RPV. The results were integrated into a numerical calculation model and a stress analysis was realized for RPV with postulated failures within cladding. For additional experimental confirmation of the investigation results, a specimen similar to the component is being prepared for examination. The main results of the investigation are presented. Under normal operating conditions crack growth in the cladding can be excluded with the failures and marginal conditions assumed here. Possible crack growth could be estimated conservatively by using e.g. CT or TPB specimens.