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Prediction of residual stress distributions due to surface machining and welding and crack growth simulation under residual stress distribution
- Source :
- Nuclear Engineering and Design. 241:1335-1344
- Publication Year :
- 2011
- Publisher :
- Elsevier BV, 2011.
-
Abstract
- In nuclear power plants, stress corrosion cracking (SCC) has been observed near the weld zone of the core shroud and primary loop recirculation (PLR) pipes made of low-carbon austenitic stainless steel Type 316L. The joining process of pipes usually includes surface machining and welding. Both processes induce residual stresses, and residual stresses are thus important factors in the occurrence and propagation of SCC. In this study, the finite element method (FEM) was used to estimate residual stress distributions generated by butt welding and surface machining. The thermoelastic-plastic analysis was performed for the welding simulation, and the thermo-mechanical coupled analysis based on the Johnson–Cook material model was performed for the surface machining simulation. In addition, a crack growth analysis based on the stress intensity factor (SIF) calculation was performed using the calculated residual stress distributions that are generated by welding and surface machining. The surface machining analysis showed that tensile residual stress due to surface machining only exists approximately 0.2 mm from the machined surface, and the surface residual stress increases with cutting speed. The crack growth analysis showed that the crack depth is affected by both surface machining and welding, and the crack length is more affected by surface machining than by welding.
- Subjects :
- Nuclear and High Energy Physics
Materials science
Mechanical Engineering
Butt welding
Metallurgy
Welding
Electric resistance welding
law.invention
Nuclear Energy and Engineering
Machining
Residual stress
law
General Materials Science
Core shroud
Stress corrosion cracking
Safety, Risk, Reliability and Quality
Waste Management and Disposal
Stress intensity factor
Subjects
Details
- ISSN :
- 00295493
- Volume :
- 241
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Design
- Accession number :
- edsair.doi...........3e98e3afe2458642453496c3d3072898