A discussion on the impact of flow accelerated corrosion on the operation and maintenance of nuclear power plants
Creators
- 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)
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)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 32038352
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CANDU TYPE REACTORS; CARBON STEELS; CORROSION PROTECTION; DIFFUSION; DISSOLUTION; MASS TRANSFER; NUCLEAR POWER PLANTS; PIPES; PWR TYPE REACTORS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; STRESS CORROSION; WATER CHEMISTRY
- Descriptors DEC
- ALLOYS; BOILERS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; COOLING SYSTEMS; CORROSION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; IRON ALLOYS; IRON BASE ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; THERMAL POWER PLANTS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 2 tabs., 5 figs.; This record replaces 31057978