Bruce A Nuclear Division -- Steam generator life management program
Following a number of steam generator tube leaks in the early 1990`s, management of the Bruce A nuclear station established the Steam Generator Program and instituted an extensive program of boiler inspection, cleaning and refurbishment. The dominant tube degradation mechanism was identified as circumferentially oriented ODSCC. However, a number of other tube degradation mechanisms were also identified as currently or potentially active. The Bruce A steam generator has a number of unique design features that both affect the degradation process and complicate the refurbishment activities. This paper will provide an overview of the steam generator design features, the degradation mechanisms, the approach adopted in three key areas of the Steam Generator Program: (1) organization, (2) strategic planning and (3) the boiler cleaning and refurbishment activities and a summary of key findings.
- OSTI ID:
- 277842
- Report Number(s):
- CONF-960306-; ISBN 0-7918-1226-X; TRN: 96:018251
- Resource Relation:
- Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 5: Radioactive waste disposal; Decontamination and decommissioning; Aging assessment and license renewals; Global advances in nuclear codes and standards; Major component reliability; Rao, A.S. [ed.] [General Electric Nuclear Energy, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 525 p.
- Country of Publication:
- United States
- Language:
- English
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