Numerical simulation of thermal stratification in an elbow branch pipe of a tee junction with and without leakage

作者: T. Lu , H.T. Li , X.G. Zhu

DOI: 10.1016/J.ANUCENE.2013.04.011

关键词:

摘要: Abstract Thermal stratification can cause thermal fatigue of the piping system a nuclear power plant. One regions most at risk suffering from is small elbow pipe branching off main coolant loop for drain or letdown in chemical and volume control (CVCS). This work focuses on fundamental description caused by turbulent penetration buoyancy effects branch using large-eddy simulations (LESs). The LES results normalized temperature, mean root-mean square (RMS) temperature were found to be good agreement with available experimental data which confirms that predict closed where cold fluids are stagnant. Subsequently, flow heat transfer numerically predicted when leakage occurred pipe. numerical show region pushed towards horizontal part may remain there long time ratio 1%. However, quickly eliminated 5%, although higher spectrum density (PSD) early stages leakage. It concluded result being high stratification.

参考文章(13)
Jeong Ik Lee, Lin-wen Hu, Pradip Saha, Mujid S. Kazimi, Numerical analysis of thermal striping induced high cycle thermal fatigue in a mixing tee Nuclear Engineering and Design. ,vol. 239, pp. 833- 839 ,(2009) , 10.1016/J.NUCENGDES.2008.06.014
Tao Lu, PX Jiang, ZJ Guo, YW Zhang, H Li, None, Large-eddy simulations (LES) of temperature fluctuations in a mixing tee with/without a porous medium International Journal of Heat and Mass Transfer. ,vol. 53, pp. 4458- 4466 ,(2010) , 10.1016/J.IJHEATMASSTRANSFER.2010.07.001
J.H. Kim, R.M. Roidt, A.F. Deardorff, Thermal stratification and reactor piping integrity Nuclear Engineering and Design. ,vol. 139, pp. 83- 95 ,(1993) , 10.1016/0029-5493(93)90263-9
Jean-Marc Ndombo, Richard J.A. Howard, Large Eddy Simulation and the effect of the turbulent inlet conditions in the mixing Tee Nuclear Engineering and Design. ,vol. 241, pp. 2172- 2183 ,(2011) , 10.1016/J.NUCENGDES.2011.03.020
Kunihiro Iida, A review of fatigue failures in LWR plants in Japan Nuclear Engineering and Design. ,vol. 138, pp. 297- 312 ,(1992) , 10.1016/0029-5493(92)90068-7
Simon Kuhn, Olivier Braillard, Bojan Ničeno, Horst-Michael Prasser, Computational study of conjugate heat transfer in T-junctions Nuclear Engineering and Design. ,vol. 240, pp. 1548- 1557 ,(2010) , 10.1016/J.NUCENGDES.2010.02.022
M. Miksch, E. Lenz, R. Löhberg, Loading conditions in horizontal feedwater pipes of LWRs influenced by thermal shock and thermal stratification effects Nuclear Engineering and Design. ,vol. 84, pp. 179- 187 ,(1985) , 10.1016/0029-5493(85)90188-8
Lin-Wen Hu, Mujid S. Kazimi, LES benchmark study of high cycle temperature fluctuations caused by thermal striping in a mixing tee International Journal of Heat and Fluid Flow. ,vol. 27, pp. 54- 64 ,(2006) , 10.1016/J.IJHEATFLUIDFLOW.2005.08.001
Toru Oumaya, Akira Nakamura, Nobuyuki Takenaka, Daisuke Onojima, Thermal Stress Evaluation of a Closed Branch Pipe Connected to Reactor Coolant Loop Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. ,vol. 2006, pp. 279- 287 ,(2006) , 10.1115/ICONE14-89799
D. Tenchine, Some thermal hydraulic challenges in sodium cooled fast reactors Nuclear Engineering and Design. ,vol. 240, pp. 1195- 1217 ,(2010) , 10.1016/J.NUCENGDES.2010.01.006