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

Fusion Engineering and Design

Volumn 81, Issue 8-14 PART B, 2006, Pages 1099-1103

  Sueishi, Y ^a   Kohyama, A ^a   Kinoshita, H ^b   Narui, M ^c   Fukumoto, K ^d  

^a KYOTO UNIVERSITY   (Japan)

^b HOKKAIDO UNIVERSITY   (Japan)

^c TOHOKU UNIVERSITY   (Japan)

^d UNIVERSITY OF FUKUI   (Japan)

Author keywords

316L; Core shroud; Stress corrosion cracking; Surface machining

Indexed keywords

BOILING WATER REACTORS; HARDNESS; MICROSTRUCTURE; NANOTECHNOLOGY;

316L; CORE SHROUD; SURFACE MACHINING;

STRESS CORROSION CRACKING;

EID: 32444445471     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.09.065     Document Type: Article

References (7)

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2. The Working Team for Examination of the Samples from Core Shrouds and Primary Loop Recirculation Piping, Report of the Sample from Core Shroud (1F4-H4) at Fukushima Dai-ichi Nuclear Power Station Unit-4, JAERI-Tech 2004-004, 2004.
3. The Working Team for Examination of the Samples from Core Shrouds and Primary Loop Recirculation Piping, Report of the Sample from Core Shroud (K1-H4) at Kashiwazaki-Kariwa Nuclear Power Station Unit-1, JAERI-Tech 2004-011, 2004.
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6. The Working Team for Examination of the Samples from Core Shrouds and Primary Loop Recirculation Piping, Report of the Sample from Core Shroud (2F3-H6a) at Fukushima Dai-ni Nuclear Power Station Unit-3, JAERI-Tech 2004-044, 2004.
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