Pipe degradation investigations for optimization of flow-accelerated corrosion inspection location selection
A large amount of piping in a typical nuclear power plant is susceptible to Flow-Accelerated Corrosion (FAC) wall thinning to varying degrees. A typical PAC monitoring program includes the wall thickness measurement of a select number of components in order to judge the structural integrity of entire systems. In order to appropriately allocate resources and maintain an adequate FAC program, it is necessary to optimize the selection of components for inspection by focusing on those components which provide the best indication of system susceptibility to FAC. A better understanding of system FAC predictability and the types of FAC damage encountered can provide some of the insight needed to better focus and optimize the inspection plan for an upcoming refueling outage. Laboratory examination of FAC damaged components removed from service at Northeast Utilities` (NU) nuclear power plants provides a better understanding of the damage mechanisms involved and contributing causes. Selected results of this ongoing study are presented with specific conclusions which will help NU to better focus inspections and thus optimize the ongoing FAC inspection program.
- OSTI ID:
- 136832
- Report Number(s):
- CONF-950740-; ISBN 0-7918-1344-4; TRN: 96:000948
- 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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