Chexal-Horowitz flow-accelerated corrosion model -- Parameters and influences
- Electric Power Research Inst., Palo Alto, CA (United States)
- DuPage Computer Applications, Inc., Woodridge, IL (United States)
Flow-accelerated corrosion (FAC) continues to cause problems in nuclear and fossil power plants. Thinning caused by FAC has lead to many leaks and complete ruptures. These failures have required costly repairs and occasionally have caused lengthy shutdowns. To deal with FAC, utilities have instituted costly inspection and piping replacement programs. Typically, a nuclear unit will inspect about 100 large bore piping components plus additional small bore components during every refueling outage. To cope with FAC, there has been a great deal of research and development performed to obtain a greater understanding of the phenomenon. Currently, there is general agreement on the mechanism of FAC. This understanding has lead to the development of computer based tools to assist utility engineers in dealing with this issue. In the United States, the most commonly used computer program to predict and control is CHECWORKS{trademark}. This paper presents a description of the mechanism of FAC, and introduces the predictive algorithms used in CHECWORKS{trademark}. The parametric effects of water chemistry, materials, flow and geometry as predicted by CHECWORKS{trademark} will then be discussed. These trends will be described and explained by reference to the corrosion mechanism. The remedial actions possible to reduce the rate of damage caused by FAC will also be discussed.
- OSTI ID:
- 136833
- Report Number(s):
- CONF-950740-; ISBN 0-7918-1344-4; TRN: 96:000949
- Resource Relation:
- Conference: Joint American Society of Mechanical Engineers (ASME)/Japan Society of Mechanical Engineers (JSME) pressure vessels and piping conference, Honolulu, HI (United States), 23-27 Jul 1995; Other Information: PBD: 1995; Related Information: Is Part Of International pressure vessels and piping codes and standards. Volume 2: Current perspectives; PVP-Volume 313-2; Rao, K.R.; Asada, Yasuhide; Adams, T.M. [eds.] [and others]; PB: 505 p.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
FOSSIL-FUEL POWER PLANTS
PIPES
BWR TYPE REACTORS
CORROSION
PWR TYPE REACTORS
NUCLEAR POWER PLANTS
FLUID FLOW
C CODES
WATER CHEMISTRY
PARAMETRIC ANALYSIS
MITIGATION
MATHEMATICAL MODELS
TEMPERATURE DEPENDENCE
MASS TRANSFER
PH VALUE
PERFORMANCE
COMPARATIVE EVALUATIONS
INSPECTION
THEORETICAL DATA