Improvement of gas entrainment evaluation method. Introduction of surface tension effect
Creators
- 1. Japan Atomic Energy Agency, Advanced Nuclear System Research and Development Directorate, Oarai, Ibaraki (Japan)
- 2. Central Research Inst. of Electric Power Industry, Civil Engineering Research Lab., Abiko, Chiba (Japan)
- 3. Univ. of Tsukuba, Dept. of Engineering Mechanics and Energy, Tsukuba, Ibaraki (Japan)
- 4. NDD Corp., Tsuchiura, Ibaraki (Japan)
Description
A gas entrainment (GE) evaluation method was presented at NTHAS5 to propose design criteria of sodium-cooled fast reactor systems. In that presentation, the GE evaluation method was confirmed to give reasonable gas code length values by simple evaluation procedures. However, in the GE evaluation method, surface tension effects were neglected for simplification. In this research, the analytical accuracy of gas core lengths is improved by introducing the surface tension effects into the GE evaluation method. For that purpose, first, the mechanical balance between gravitational, centrifugal and surface tension forces is considered and second, the shape of a gas core tip is approximated by a quadratic function. Finally, using a curvature calculated from the approximated gas core shape, we can determine the gas core length satisfying the mechanical balance. This improved GE evaluation method for gas core lengths is validated by analyzing the gas core lengths observed in basic experiments. As the results, the analytical gas core length values by the improved GE evaluation method become shorter and give better agreements with the experimental data than the original GE evaluation method. In addition, the experimental data under different temperature and surfactant concentration conditions are reproduced by the improved GE evaluation method. (author)
Additional details
Publishing Information
- Imprint Title
- NTHAS6: Proceedings of the 6th Japan-Korea symposium on nuclear thermal hydraulics and safety
- Imprint Pagination
- 818 p.
- Journal Page Range
- [8 p.]
Conference
- Title
- 6. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS6
- Dates
- 24-27 Nov 2008
- Place
- Nago, Okinawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43020201
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCURACY; COMPUTERIZED SIMULATION; ENTRAINMENT; EVALUATION; FAST REACTORS; FLUID MECHANICS; GASES; NAVIER-STOKES EQUATIONS; NUMERICAL ANALYSIS; REACTOR VESSELS; SODIUM COOLED REACTORS; SURFACE TENSION
- Descriptors DEC
- CONTAINERS; DIFFERENTIAL EQUATIONS; EPITHERMAL REACTORS; EQUATIONS; FLUIDS; LIQUID METAL COOLED REACTORS; MATHEMATICS; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; REACTORS; SIMULATION; SURFACE PROPERTIES
Optional Information
- Notes
- This USB flash memory can be used for WINDOWS 2000/XP, MACINTOSH 9.x/10.x; Acrobat Reader is included; Data in PDF format, Folder Name: FullPaper, Paper ID: N6P1052.pdf; 14 refs., 4 figs., 2 tabs.