CFD analysis of turbulent flow in a PWR feedwater suction line for the prediction of local area susceptible to FAC-caused wall thinning
Creators
- 1. Korea Inst. of Nuclear Safety, Daejeon (Korea, Republic of)
Description
Many of failures caused by wall thinning in carbon steel piping systems/components have been experienced worldwide and occurred in most of types of nuclear power plants. It has been well known that such wall thinning is caused by the flow-accelerated corrosion (FAC). Especially, intensive research to understand the parameters affecting FAC was initiated from Surry unit 2 wall thinning failure in 1986 and many regulatory technologies have been developed to guarantee the integrity of piping systems/components since the accident occurrence. In this work the flow field inside piping system with the same geometrical and flow conditions as those of the failed pipe at the Surry unit 2 was analyzed and the shear stress distributions was calculated to predict the local region of pipe wall highly susceptible to FAC-caused wall thinning by using computational fluid dynamics (CFD). For a real accident, break initiated in the connection region of straight pipe and elbow near the inlet part of bend which was the thinnest area, which accords with weak region expected by CFD analysis. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [4 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39099906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATION; C CODES; COMPUTERIZED SIMULATION; CORROSION DENTING; FEEDWATER; FINITE ELEMENT METHOD; FLUID FLOW; FLUID MECHANICS; NUMERICAL ANALYSIS; PIPES; PWR TYPE REACTORS; RUPTURES; SURRY-2 REACTOR; TURBULENT FLOW
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DEFORMATION; ENRICHED URANIUM REACTORS; FAILURES; FLUID FLOW; HYDROGEN COMPOUNDS; MATHEMATICAL SOLUTIONS; MATHEMATICS; MECHANICS; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, PaperID ICONE15-10869.pdf; 5 refs., 11 figs., 1 tab.