Effective flow-accelerated corrosion programs in nuclear facilities
Creators
- 1. Altran Corporation, Boston, MA (United States)
Description
Piping Flow-Accelerated Corrosion Programs in nuclear power generation facilities are classically comprised of the selection of inspection locations with the assistance of a predictive methodology such as the Electric Power Research Institute computer codes CHECMATE or CHECWORKS, performing inspections, conducting structural evaluations on the inspected components, and implementing the appropriate sample expansion and corrective actions. Performing such a sequence of steps can be effective in identifying thinned components and implementing appropriate short term and long term actions necessary to resolve flow-accelerated corrosion related problems. A maximally effective flow-accelerated corrosion (FAC) program requires an understanding of many programmatic details. These include the procedural control of the program, effective use of historical information, managing the activities performed during a limited duration outage, allocating resources based on risk allocation, having an acute awareness of how the plant is operated, investigating components removed from the plant, and several others. This paper will describe such details and methods that will lead to a flow-accelerated corrosion program that effectively minimizes the risk of failure due to flow-accelerated corrosion and provide full and complete documentation of the program. (author)
Files
35097916.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2
- Imprint Pagination
- 814 p.
- Journal Page Range
- p. 47A1-47A6
- Report number
- INIS-XA-N--081
Conference
- Title
- 4. international topical meeting on nuclear thermal hydraulics, operations and safety
- Dates
- 5-8 Apr 1994
- Place
- Taipei, Taiwan (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35097916
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; CORROSION; FAILURES; FLOW RATE; MONITORING; REACTOR COMPONENTS
- Descriptors DEC
- CHEMICAL REACTIONS; COMPUTER CODES
Optional Information
- Notes
- This record replaces 35095649; 3 refs, 1 fig