Unsteady hydraulic characteristics in large-diameter pipings with elbow for JSFR. (1) Current status of flow-induced vibration evaluation methodology development for the JSFR pipings
Creators
- 1. Japan Atomic Energy Agency, Advanced Nuclear System Research and Development Directorate, Oarai, Ibaraki (Japan)
- 2. Mitsubishi FBR Systems, Inc., Tokyo (Japan)
Description
This paper describes the current status of flow-induced vibration evaluation methodology development for the primary piping in JSFR, in particular emphasizing on the development approach and research activities that investigate unsteady hydraulic characteristics in a short-elbow piping. Experimental efforts have been made using 1/3-scale and 1/10-scale single-elbow test sections for the hot-leg piping and 1/4-scale and 1/7-scale triple-elbow test sections for the cold-leg piping. Recent experiments using the 1/3-scale test section revealed that a swirl flow at the inlet of the hot-leg piping hardly influenced the pressure fluctuations onto the pipe. Simulation activities include Unsteady Reynolds Averaged Navier Stokes equation (U-RANS) and Large Eddy Simulation (LES) approaches. Numerical results using the U-RANS approach appear in this paper, indicating its applicability to the hot-leg piping experiments. (author)
Additional details
Publishing Information
- Imprint Title
- NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
- Imprint Pagination
- [4617 p.]
- Journal Page Range
- [18 p.]
Conference
- Title
- 13. international topical meeting on nuclear reactor thermal hydraulics
- Acronym
- NURETH-13
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Kanazawa, Ishikawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43036677
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- HYDRAULIC TRANSPORT; LARGE-EDDY SIMULATION; LMFBR TYPE REACTORS; MECHANICAL VIBRATIONS; NAVIER-STOKES EQUATIONS; PIPES; PRIMARY COOLANT CIRCUITS; SODIUM COOLED REACTORS; UNSTEADY FLOW; VORTEX FLOW
- Descriptors DEC
- BREEDER REACTORS; COMPUTERIZED SIMULATION; COOLING SYSTEMS; DIFFERENTIAL EQUATIONS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EQUATIONS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; LIQUID METAL COOLED REACTORS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; TRANSPORT; TUBES
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1186.pdf