Numerical calculations on countercurrent gas-liquid flow in a PWR hot leg. (2) Steam-water flow under PWR plant conditions
- 1. Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
- 2. Kobe University, Kobe, Hyogo (Japan)
Description
In order to improve the countercurrent flow model of a transient analysis code, countercurrent air-water tests were previously conducted using a 1/15th scale model of the PWR hot leg at Kobe University. Then numerical calculations were made of the test results using the thermal-hydraulic analysis code FLUENT6.3.26 and an Euler-Euler model. The calculated flow patterns in the hot leg were quite similar to the observed results, and the calculated CCFL (countercurrent flow limitation) characteristics agreed well with the measured data. In the present study, we carried out numerical calculations for steam-water flow under PWR plant conditions. The calculated flow patterns in the hot leg were similar to the observed results in the 1/15th scale air-water tests. Furthermore, the calculated CCFL characteristics correlated with Wallis parameters agreed well with the data by the 1/15th scale air-water tests and the full-scale steam-water UPTF tests. The results indicate that the correlations used for the gas-liquid interfacial friction are valid. (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
- [9 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
- 43105850
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CORRELATIONS; COUNTER CURRENT; FLOW MODELS; FRICTION; GAS FLOW; LIQUID FLOW; LIQUIDS; NUMERICAL ANALYSIS; PWR TYPE REACTORS; RHR SYSTEMS; SCALE MODELS; STEAM; THERMAL HYDRAULICS; TRANSIENTS; WATER
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; FLUIDS; HYDRAULICS; HYDROGEN COMPOUNDS; MATHEMATICAL MODELS; MATHEMATICS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1040.pdf; 17 refs., 7 figs.