Numerical simulations of pressure fluctuations at branch piping in BWR main steam line
- 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan)
- 2. Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki (Japan)
- 3. Hitachi, Ltd., Energy and Environmental Laboratory, Hitachi, Ibaraki (Japan)
Description
The power uprating of a nuclear power plant may increase/accelerate degradation phenomena such as flow-induced vibration and wall thinking. A steam dryer was damaged by a high cycle fatigue due to an acoustic-induced vibration at the branch piping of safety relief valves (SRVs) in main steam lines. In this study, we conducted the numerical simulations of steam/air flow around a simplified branch piping to clarify the basic characteristics of resonance. LES simulations were conducted in ordinary pressure/temperature air and steam under BWR plant conditions. In both cases, the excitation of the pressure fluctuations at the branch was observed under some inlet velocity conditions. These fluctuations and inlet conditions were normalized and the obtained results were compared. The normalized results showed that the range and maximum amplitude of pressure fluctuations were almost the same in low-pressure/temperature air and high-pressure/temperature steam. We found that ordinary pressure/temperature air experiments and simulations can possibly clarify the characteristics of the resonance in high-pressure/temperature steam. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of 2009 international congress on advances in nuclear power plants
- Imprint Pagination
- [2572 p.]
- Journal Page Range
- [7 p.]
- Report number
- INIS-JP--123
Conference
- Title
- 2009 international congress on advances in nuclear power plants
- Acronym
- ICAPP2009
- Dates
- 10-14 May 2009
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43084306
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR FLOW; BWR TYPE REACTORS; FATIGUE; FLUCTUATIONS; LARGE-EDDY SIMULATION; PIPES; RELIEF VALVES; RESONANCE; STEAM; STEAM LINES
- Descriptors DEC
- COMPUTERIZED SIMULATION; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FLUID FLOW; GAS FLOW; MECHANICAL PROPERTIES; PIPELINES; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES; VALVES; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9372.pdf; 8 refs., 9 figs., 1 tab.