Published July 2008 | Version v1
Miscellaneous

Probabilistic structural integrity assessment of reactor coolant pressure boundary piping. 2. Residual stress analyses of the effect of scatter of welding conditions

  • 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)

Description

Stress corrosion cracking (SCC) in primary loop recirculation piping made of austenitic stainless steel has been observed near welding joints. The SCC grows near the welding zone mainly due to high tensile residual stress by welding as well as the other contributing factors of material and environment. The residual stress analysis due to welding of austenitic stainless piping is important and has been already conducted by many researchers. In present work, the effect of scatters of welding conditions such as heat input and welding speed on residual stress have been evaluated by parametric FEM analyses considering the variation of some parameters based on the welding experiments. The effects of welding conditions on crack growth behavior have been also evaluated by SCC growth simulations using calculated residual stress distributions and a procedure in the fitness-for-service code. Welding parameters such as heat input and welding speed have a strong influence on crack growth rate since residual stress is also affected by scatter of these welding parameters. (author)

Part of:
Proceedings of the 5th annual meeting of Japan Society of Maintenology

Additional details

Additional titles

Original title (Japanese)
Nippon hozen gakkai dai-5-kai gakujutsu koenkai yoshishu

Publishing Information

Imprint Title
Proceedings of the 5th annual meeting of Japan Society of Maintenology
Imprint Pagination
551 p.
Journal Page Range
p. 427-430

Conference

Title
5. annual meeting of Japan Society of Maintenology
Dates
10-12 Jul 2008
Place
Mito, Ibaraki (Japan)

Optional Information

Notes
7 refs., 4 figs., 1 tab. Imprint:Nippon hozen gakkai dai-5-kai gakujutsu koenkai yoshishu