A two-phase methodology to predict FAC wear sites in the piping system of a BWR
Creators
- 1. Department of Engineering and System Science, National Tsing Hua University, 101, Sec. 2, Kuang-Fu Road, Hsingchu 30013, Taiwan 325 (China)
- 2. Department of Mechanical and Automation Engineering, I-Shou University, Kaohsiung County, Taiwan (China)
Description
Flow accelerated corrosion (FAC) wear is a serious degradation problem especially for nuclear power plants since it may result in the plant damage as well as risk to personnel. In this paper, a methodology which includes the two-phase hydrodynamic CFD models and FAC models, is proposed to predict severe FAC wear sites. Based on hydrodynamic simulation results, the present CFD models can precisely capture the two-phase characteristics within the piping system, which include the centrifugal effect, the gravitation effect and the imbalance of phase and mass separation in a T-junction, etc. Coupled with these flow characteristics, the appropriate FAC indicators can predict the possible locations of severe FAC wear. This methodology was validated against the measured results of wear site distributions for the piping system in a boiling water reactor (BWR) power plant. Good agreement between measurements and predictions at severe wear sites indicate that the present models can capture the characteristics of severe FAC wear and can help assist in the pipe wall-monitoring program for a nuclear power plant
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2008.03.012Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2008.03.012;
- PII
- S0029-5493(08)00179-9;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 238
- Journal Issue
- 9
- Journal Page Range
- p. 2189-2196
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40005620
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- BWR TYPE REACTORS; CAPTURE; CORROSION; DAMAGE; DISTRIBUTION; FORECASTING; GRAVITATION; HAZARDS; MONITORING; NUCLEAR POWER PLANTS; PERSONNEL; SIMULATION; WALLS; WEAR
- Descriptors DEC
- CHEMICAL REACTIONS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.