Numerical Calculations for Steam-Water CCFL Tests Using the 1/3rd Scale Rectangular Channel Simulating a PWR Hot Leg
In reflux condensation, steam generated in the reactor core and water condensed in a steam generator (SG) form a countercurrent flow in a hot leg, which consists of a horizontal pipe, an elbow and an inclined pipe. At Forschungszentrum Dresden-Rossendorf (FZD), both countercurrent air-water and steam-water tests were previously carried out using the 1/3rd scale rectangular channel simulating a PWR hot leg installed in the pressure chamber of the TOPFLOW facility. In this paper, in order to evaluate the effects of fluid properties, numerical calculations for the steam-water CCFL (countercurrent flow limitation) tests at FZD were conducted using the CFD code, FLUENT6.3.26. The numerical calculation region included the reactor vessel simulator, hot leg and SG inlet chamber, in order to avoid uncertainties of boundary conditions at both ends of the hot leg. The VOF (volume of fluid) method and twofluid (2F) model were used. In the 2F model, the combination of three correlations on the interfacial friction coefficients, which had been validated for the 1/15th and 1/5th scale tests at Kobe University, was used as a function of local void fractions. The CCFL characteristics calculated by the 2F and VOF agreed with the steam-water CCFL data at FZD and showed the same trends with the data for fluid properties.
reflux condensation PWR hot leg countercurrent flow steam-water experiment numericalcalculation
Ikuo Kinoshita Michio Murase Yoichi Utanohara Dirk Lucas Christophe Vallée Akio Tomiyama
Institute of Nuclear Safety System, Incorporated 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Ja Forschungszentrum Dresden-Rossendorf e. V. P.O.Box 510 119, D-01314 Dresden, Germany Kobe University 1-1 Rokkodai, Nada-ku, Kobe-shi, Hyogo 657-8501, Japan
国际会议
上海
英文
165-177
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）