Microstructure and nano-hardness analyses of stress corrosion cracking, utilizing 316L core shroud of BWR power reactors

The water cooled shield blanket made of Type 316L SS for the international thermonuclear experimental reactor (ITER) has potential issues related to stress corrosion cracking (SCC). Shroud mock-ups and boat samples taken from the core shroud of the boiling water reactor (BWR) with SCC were investiga...

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Bibliographic Details
Published in:Fusion engineering and design 2006-02, Vol.81 (8), p.1099-1103
Main Authors: Sueishi, Y., Kohyama, A., Kinoshita, H., Narui, M., Fukumoto, K.
Format: Article
Language:English
Subjects:
316L
Applied sciences
Controled nuclear fusion plants
Core shroud
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Installations for energy generation and conversion: thermal and electrical energy
Stress corrosion cracking
Surface machining
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Summary:The water cooled shield blanket made of Type 316L SS for the international thermonuclear experimental reactor (ITER) has potential issues related to stress corrosion cracking (SCC). Shroud mock-ups and boat samples taken from the core shroud of the boiling water reactor (BWR) with SCC were investigated from the viewpoint of microstructures and nano-hardness. Fine grains and deformation bands were observed in the hardened surface thin layers of the shroud mock-up, where hardness profiles in the ground portion was different from those in the milled portion. In the fine grain region, crevices were found only in the ground surface. In the core shroud, hardened surface regions were also found. Results showed that the crevices found on the ground surface could be one possible factor for SCC initiation.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2005.09.065