管型对波动管热分层现象的影响分析

doi:10.7538/yzk.2013.47.10.1760

摘要/Abstract

摘要：

为分析评价压水堆核电厂稳压器波动管管型对热分层现象的影响，提出采用螺纹管来减弱热分层的措施。利用计算流体力学（CFD）分析方法，对升温、升压阶段波动管原型和改进模型的热分层现象进行数值模拟，得到两种模型不同波动流速下沿波动管轴线方向的截面最大温差分布以及流场分布。对比分析结果表明：波动管结构由光管改为螺纹管后流场紊动加强并出现涡流，冷热流体间的混合增强，与原型相比可使波动管的截面温差减小约1/3，从而有效地减弱热分层的影响。

关键词: 波动管, 热分层, 螺纹管, 计算流体力学

Abstract:

In order to analyze and evaluate the effect of pipe type on thermal stratification for PWR pressurizer surge line, computational fluid dynamics (CFD) method was used for the current and improved screw surge line during heating up condition. The maximum temperature differences and velocity distribution along the surge line axis under different velocities were obtained. Comparative analysis indicates that replacing current smooth tube with screw pipe can enhance the turbulent flow and the mixing effects between the hot and cold fluids. The temperature differences in flow cross sections along the screw surge line axis are reduced by about 1/3 compared with current smooth surge line, yielding effectively mitigation to the influence of thermal stratification.

Key words: surge line, thermal stratification, screw surge line, computational fluid dynamics

乔守旭;王海军;顾红芳;张磊;罗毓珊. 管型对波动管热分层现象的影响分析[J]. 原子能科学技术, 2013, 47(10): 1760-1765.

QIAO Shou-xu;WANG Hai-jun;GU Hong-fang;ZHANG Lei;LUO Yu-shan. Analysis of Effect of Pipe Type on Surge Line Thermal Stratification[J]. Atomic Energy Science and Technology, 2013, 47(10): 1760-1765.

参考文献

［1］YU Y J, PARK S H, SOHN G H, et al. Structural evaluation of thermal stratification for PWR surge line［J］. Nuclear Engineering and Design, 1997, 178(2): 211-220.
［2］USNRC. Pressurizer surge line thermal stratification, NRCB 88-11［R/OL］. http:∥www.nrc.gov/reading-rm/doc-collections/gen-comm/bulletins/1988/bl88011.html.
［3］USNRC.Thermal stresses in piping connected to reactor coolant systems, NRC bulletin 88-08［R/OL］. http:∥www.nrc.gov/reading-rm/doc-collections/gen-comm/bulletins/1988/bl88008s1.html.
［4］赖建永,黄伟. 布置方式对波动管热分层现象的影响分析［J］. 核动力工程,2011,32(6):47-50.LAI Jianyong, HUANG Wei. Effect of layout on surge line thermal stratification［J］. Nuclear Power Engineering, 2011, 32(6): 47-50（in Chinese）.
［5］JEONG I S. Thermal stratification in a horizontal circular cylinder with external heat tracing［J］. Numerical Heat Transfer A: Applications, 1999, 35(1): 85-98.
［6］SUNDHEIMER P. Device for preventing thermal stratification in a steam generator feed pipe: France, 4870927［P］. 1988-06-30.
［7］JEONG I S, HA G H. Flow mixing device for mitigating thermal stratification in pipe, includes pipe, flange and guiding hole, where guiding hole is formed at upper side of flow mixing device: Korea, KR2012001413-A［P］. 2012-01-04.
［8］ANSYS Inc. ANSYS CFX-solver theory guide: Southpointe, 275 technology drive, canonsburg, PA 15317［M/OL］. (2011-11-10). http:∥www.ansys.com.
［9］ENSEL C, COLAS A, BARTHEZ M. Stress analysis of a 900 MW pressurizer surge line including stratification effects［J］. Nuclear Engineering and Design, 1995, 153(2-3): 197-203.
［10］NAVARRO M A, REZENDE H C, SANTOS A A C D, et al. Numerical and experimental simulation of the thermal stratification in a horizontal pipe［J］. J Trans Phenomena, 2008, 10: 215-221.

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