MPA – University of Stuttgart, Stuttgart, Germany

Georg Veile

Biography

Georg Veile is working at MPA Stuttgart as research assistant and project leader. In his PhD thesis he improved the fatigue life assessment of nuclear reactor internals and their welds.

Conferences

Room

Date

Hour

Subject

Room 10

20-11-2025

11:15 am – 11:45 am

10 Improving fatigue life assessment of scanned nuclear grade weld topologies using elastic-plastic FEA and advanced gradient based fatigue damage parameters

Room 8

19-11-2025

6:00 pm – 6:30 pm

69 Ultrasonic fatigue testing of austenitic stainless steels up to a very high number of laod cycles

Conferences Details

10 Improving fatigue life assessment of scanned nuclear grade weld topologies using elastic-plastic FEA and advanced gradient based fatigue damage parameters

Fatigue life prediction of scanned weld geometries can be less accurate than prediction using an idealised weld radius. One possible solution is the use of elastic plastic material models. Furthermore, the accuracy can be improved by adjusting the material model retrospectively. However, this cannot be applied to fatigue life prediction in industry. An alternative solution is to introduce additional factors that take into account stress, strain or shear gradients and geometric factors. Scanned weld topologies show radii of up to 0.1mm in the critical areas. These radii can be smaller than the grain size of the base metal. To investigate the difference in accuracy between scanned and idealised weld geometries, we examined the effect of smoothing the scanned surfaces. We also determined different gradients and found the cause of the non-conservative fatigue life prediction in the FDPRM and FDPFFS. The subsequent effect on FDPFS, FDPFGF, FDTSWT was also investigated

69 Ultrasonic fatigue testing of austenitic stainless steels up to a very high number of laod cycles

Austenitic stainless steels are often used for reactor internals that are subject to mechanical and thermo-mechanical stresses that induce low cycle fatigue (LCF), high cycle fatigue (HCF) and even very high cycle fatigue (VHCF). LCF occurs, for example, in piping materials during heating and cooling cycles in start-up and shutdown operations due thermal stratification. Some nuclear power plant components are additionally subjected to high frequency loading in the HCF/VHCF regime e.g., by thermal striping and flow induced vibrations and their interaction. To investigate the VHCF regime mechanical cyclic loading up to 1010 is required. Therefore, ultrasonic fatigue testing systems (UFTS) with a test frequency of f = 20 kHz are usually used. While LCF and HCF tests are strain or stress controlled, VHCF tests are displacement controlled. Calculation from displacement amplitude to strain/stress amplitude is required. In contrast to high-strength steels and other metallic materials such as aluminium and titanium alloys, displacement-controlled VHCF tests on ASS and UFTS cause serious problems in adjusting the control and test parameters due to the elastic plastic behaviour and, for metastable ASSs, the phase transformation from gamma-austenite into alpha’-martensite. To compare VHCF test results to the ASME standard fatigue curve (total strain amplitude vs. load cycles to failure), a fictitious-elastic and an elastically plastic assessment method was used. The elaborated elastic–plastic assessment method generates good results, while a purely elastic assessment in the VHCF regime, commonly used in literature, leads to significantly nonconservative results. In this work, cyclic loading ap up to the VHCF regime was carried out on AISI 347 and AISI 304L at ambient temperature with load ratio R = -1 using a self-developed UFTS. During fatigue, elastic-plastic deformation occurs in the specimen, which leads to deformation-induced phase transformation and cyclic hardening. The change in the microstructure were investigated in the details using optical and scanning electron microscopy as well as non-destructive magnetic Feritscope measurements.

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