Title of article :
Fracture mechanics concepts for evaluation of irradiated reactor pressure vessel material behavior
Author/Authors :
Kussmaul، K. نويسنده , , Beyer، J. Fohl, H. نويسنده ,
Issue Information :
دوهفته نامه با شماره پیاپی سال 1999
Abstract :
The evaluation of critical circumferential through-wall crack lengths in piping is usually performed by the flow stress concept, plastic limit load method or GE-EPRI procedures. Most of these methods treat the secondary stresses. especially those caused by bending moments resulting from restrained thermal expansion, as force-controlled loads. In reality, there is a movement of the piping into the direction of the prescribed displacement and, therefore, a relaxation of the cracked section, which is due to the local rotation of the cracked section. Instead of the bending moment originating from the elastic analysis of the piping system there will be a reduced bending moment, the load decreases, the real critical through-wall crack lengths due to this displacement-controlled loading are larger than those predicted by the load controlled methods. A corresponding analytical procedure taking into account this relaxation was developed and validated by a comparison with experiments as well as finite element calculations. The procedure can be used for the evaluation of the safety of piping systems (e.g. leak-before-break analyses), if the usual methods based on force-controlled loads give unrealistic conservative results. © 1999 Elsevier Science S.A. All rights reserved.
Keywords :
Weld metal , Base material , Charpy impact test , Fracture mechanics test , Drop-weight test , Heat affected zone (HAZ) , Light water reactor , Neutron irradiation , RPV , Crack arrest , reference temperature
Journal title :
Nuclear Engineering and Design
Journal title :
Nuclear Engineering and Design