Steam generator issues in the United States
- NRC, Washington, DC (United States)
Alloy 600 steam generator tubes in the US have exhibited degradation mechanisms similar to those observed in other countries. Effective programs have been implemented to address several degradation mechanisms including: wastage; mechanical wear; pitting; and fatigue. These degradation mechanisms are fairly well understood as indicated by the ability to effectively mitigate/manage them. Stress corrosion cracking (SCC) is the dominant degradation mechanism in the US. SCC poses significant inspection and management challenges to the industry and the regulators. The paper also addresses issues of research into SCC, inspection programs, plugging, repair strategies, water chemistry, and regulatory control. Emerging issues in the US include: parent tube cracking at sleeve joints; detection and repair of circumferential cracks; free span cracking; inspection and cracking of dented regions; and severe accident analysis.
- Research Organization:
- CH2M Hill, Gainesville, FL (United States); Argonne National Lab. (ANL), Argonne, IL (United States)
- OSTI ID:
- 467892
- Report Number(s):
- NUREG/CP-0154; ANL-96/14; NEA/CNRA/R-(96)1; CONF-9510423-; ON: TI97004312; TRN: 97:008358
- Resource Relation:
- Conference: CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995; Other Information: PBD: Feb 1997; Related Information: Is Part Of Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants; Diercks, D.R. [Argonne National Lab., IL (United States)]; PB: 621 p.
- Country of Publication:
- United States
- Language:
- English
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