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Correlation for countercurrent flow limitation in a PWR hot leg |
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| Authors: | Michio Murase Akio Tomiyama Dirk Lucas Ikuo Kinoshita Yoichi Utanohara Chihiro Yanagi |
| Affiliation: | 1. Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho , Mikata-gun , Fukui , 919-1205 , Japan murase@inss.co.jp;3. Graduate School of Engineering, Kobe University , 1-1 Rokkodai, Nada-ku , Kobe , 657-8501 , Japan;4. Institute of Fluid Dynamics, Helmholtz-Zentrum Dresden-Rossendorf , P.O.Box 510 119, D-01314 , Dresden , Germany;5. Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho , Mikata-gun , Fukui , 919-1205 , Japan;6. Graduate School of Engineering, Kobe University , 1-1 Rokkodai, Nada-ku , Kobe , 657-8501 , Japan;7. Institute of Nuclear Technology, Institute of Nuclear Safety System, Inc., 64 Sata, Mihama-cho , Mikata-gun , Fukui , 919-1205 , Japan |
| Abstract: | Numerical simulations were done to evaluate countercurrent flow limitation (CCFL) characteristics in a pressurized water reactor (PWR) hot leg with the diameter of 750 mm by using a volume of fluid (VOF) method implemented in the CFD software, FLUENT6.3.26. The calculated CCFL characteristics agreed well with known values including the UPTF data at 1.5 MPa. Sensitivity analyses for system pressures up to 8 MPa showed that the calculated CCFL characteristics in the Wallis diagram were slightly mitigated from 0.1 MPa to 1.5 MPa with increasing system pressure, but they did not change from 1.5 MPa to 8MPa. Using the CCFLs calculated in this study and values measured under air–water and steam–water conditions, a CCFL correlation and its uncertainty were derived. |
| Keywords: | reflux condensation PWR hot leg countercurrent gas–liquid flow CCFL numerical simulation |