Revista17th European Conference on Fracture 2008: Multilevel Approach to Fracture of Materials, Components and Structures
Año de publicación2008
On the fatigue stress range calculations with on-line monitoring systems in nuclear power plantsCicero González, Román | Gorrochategui Sánchez, Iñaki | Cicero González, Sergio | Álvarez Laso, José Alberto |
Nuclear power plants are generally designed and inspected according to the ASME Code. This code indicates the stress intensity (SINT) as the parameter to be used in the stress analysis of components. One of the particularities of SINT is that it always takes positive values, independently of the sign of the stress (tensile or compressive). This circumstance is relevant in the Fatigue Monitoring Systems used in nuclear power plants, due to the manner the different variable stresses are combined in order to obtain the final total stress range. This paper describes some situations derived from the application of the ASME Code, shows different ways of dealing with them and illustrates their influence in the evaluation of the fatigue usage through the application to a practical example.