Published 2000 | Version v1
Miscellaneous

A discussion on the impact of flow accelerated corrosion on the operation and maintenance of nuclear power plants

  • 1. Nuclear Power Lab., Korea Electric Power Research Institute, Taejon (Korea, Republic of)

Description

FAC (Flow Accelerated Corrosion) is a type of chemical dissolution of carbon steel in high temperature water under reducing atmosphere, accelerated by fast flow. Enhanced mass transfer of ferrous ions through the diffusion layer at the oxide-water interface is the mechanism of the accelerating effect of flow. FAC impacts operation and maintenance of nuclear power plants significantly. Typical examples are wall thinning of secondary side piping, ingress of sludge into the steam generators, and wall thinning of feeder pipes and increase in reactor inlet header temperature in CANDU plants. Significance of those impacts is reviewed, and current status of plant management program is discussed. Development of a reliable FAC model to predict feeder wall thinning should be a major target of research activities in the future. Development of mitigation measures including water chemistry optimization is another topic to be challenged. (author)

Part of:
Proceedings of the Symposium on Nuclear Materials and Fuel 2000

Additional details

Publishing Information

Publisher
Korea Atomic Energy Research Institute
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of Symposium on Nuclear Materials and Fuel 2000
Imprint Pagination
1167 p.
Journal Page Range
p. 1052-1062

Conference

Title
Symposium on Nuclear Materials and Fuel 2000
Dates
24-25 Aug 2000
Place
Taejon (Korea, Republic of)

Optional Information

Notes
5 refs., 2 tabs., 5 figs.; This record replaces 31057978