NUMERICAL CALCULATIONS FOR AIR-WATER TESTS ON CCFL IN DIFFERENT-SCALE MODELS OF A PWR HOT LEG
Air-water CCFL (countercurrent flow limitation) tests using the 1/5th scale rectangular channel and 1/15th scale circular tube simulating a PWR hot leg and both air-water and steam-water CCFL tests using the 1/3rd scale rectangular channel were previously carried out at Kobe University and Forschungszentrum Dresden-Rossendorf (FZD), respectively. In this paper, numerical calculations for the air-water CCFL tests at FZD using FLUENT6.3.26 are presented and compared with the experimental data at Kobe University and FZD. In the calculations, the VOF (volume of fluid) model or two-fluid (2F) model was used. Major results were as follows: (1) the calculated CCFL characteristics using the 2F model for the FZD tests agreed well with the 1/15th scale circular tube data obtained at Kobe University and the calculated results for full-scale PWR conditions, which supported the validity of the 1/3rd scale rectangular channel to simulate CCFL in circular tubes; and (2) comparison with the FZD data showed that the calculations using the 2F and VOF models overestimated the falling water flow rates.ates.
Michio Murase Ikuo Kinoshita Yoichi Utanohara Dirk Lucas Christophe Vallée Akio Tomiyama
Institute of Nuclear Safety System, Inc.(INSS)64 Sata, Mihama-cho, Mikata-gun,Fukui 919-1205, Japan INSS 64 Sata, Mihama-cho, Mikata-gun,Fukui 919-1205, Japan Forschungszentrum Dresden-Rossendorf e.V.(FZD)D-01314 Dresden, Germany FZD D-01314 Dresden, Germany Kobe University 1-1 Rokkodai, Nada, Kobe-shi, Hyogo 657-8501, Japan
国际会议
18th International Conference on Nuclear Engineering(第18届国际核能工程大会 ICONE 18)
西安
英文
1-9
2010-05-17（万方平台首次上网日期，不代表论文的发表时间）