

浏览全部资源
扫码关注微信
1.Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin 150001, Heilongjiang, China
2.Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, Sichuan, China
Received:18 April 2019,
Revised:2019-08-02,
Published:05 November 2019
移动端阅览
孙建闯, 曹夏昕, 冉旭, 张卓华, 米争鹏, 丁铭. 低流量下等高差自然循环系统倒流现象实验研究[J]. 化工学报, 2019, 70(11): 4231-4237
SUN Jianchuang, CAO Xiaxin, RAN Xu, ZHANG Zhuohua, MI Zhengpeng, DING Ming. Experimental research on reverse flow phenomenon in natural circulation with equal height difference under low flow rate[J]. CIESC Journal, 2019, 70(11): 4231-4237
孙建闯, 曹夏昕, 冉旭, 张卓华, 米争鹏, 丁铭. 低流量下等高差自然循环系统倒流现象实验研究[J]. 化工学报, 2019, 70(11): 4231-4237 DOI: 10.11949/0438-1157.20190407.
SUN Jianchuang, CAO Xiaxin, RAN Xu, ZHANG Zhuohua, MI Zhengpeng, DING Ming. Experimental research on reverse flow phenomenon in natural circulation with equal height difference under low flow rate[J]. CIESC Journal, 2019, 70(11): 4231-4237 DOI: 10.11949/0438-1157.20190407.
自然循环系统由于具有固有安全性而被广泛应用于核电站中。等高差自然循环系统是一种特殊的系统,其加热段与水箱之间是通过上下水平段连接。在低流量条件下,这类自然循环系统会发生水箱冷水倒流至上水平段的现象,目前对该现象的研究并不常见。对等高度差自然循环系统的上水平段倒流特性进行了可视化实验研究。实验结果表明,上水平段倒流长度随流量的增加而减小,随着加热段出口流体与倒流流体温差的增大而增加。研究发现,上水平段倒流现象主要受加热段出口流体惯性力和与倒流流体形成的浮升力共同影响,并且倒流现象的发生可以通过Richardson数来判定。
Natural circulation systems are widely used in nuclear power plants due to their inherent safety. Natural circulation system with equal height different is a special system
because its heating section and water tank are connected by upper and lower horizontal loops. However
the phenomenon that the water in water tank reversely flows to the upper horizontal loop will be occurred in this kind of natural circulation system under low flow rate conditions. The studies of this phenomenon are not common. The reverse flow characteristics of upper horizontal loop is researched by visualization experiments. The results show that the reverse flow length in the upper horizontal loop decreases with the increase of flow rate
and increases with the increase of temperature difference between the outlet fluid of heater and the reverse flow fluid form water tank. It is found that the reverse flow in the upper horizontal loop is mainly affected by the inertia force of the hot water and the buoyancy force formed by the hot water and the reverse flow fluid. In addition
the reverse flow phenomenon in the upper horizontal loop can be judged by Richardson number.
吕应中 . 大规模替代化石及其他有限能源的固有安全高温核动力 [J]. 核科学与工程 , 2011 , 31 ( 1 ): 1 - 8 .
Lyu Y Z . An inherently-safe high-temperature nuclear energy producing process for the replacement of fossil and other depletive energy on a large scale [J]. Chinese Journal of Nuclear Science and Engineering , 2011 , 31 ( 1 ): 1 - 8 .
侯晓凡 , 孙中宁 , 孙秋南 , 等 . 开式自然循环系统中间歇喷泉流动的实验研究 [J]. 哈尔滨工程大学学报 , 2016 , 37 ( 4 ): 556 - 561 .
Hou X F , Sun Z N , Sun Q N , et al . Experimental study on geysering in an open natural circulation system [J]. Journal of Harbin Engineering University , 2016 , 37 ( 4 ): 556 - 561 .
鄢炳火 , 于雷 , 张杨伟 , 等 . 简谐海洋条件下自然循环运行特性 [J]. 原子能科学技术 , 2009 , 43 ( 3 ): 230 - 236 .
Yan B H , Yu L , Zhang Y W , et al . Natural circulation operational characteristics under ocean condition [J]. Atomic Energy Science and Technology , 2009 , 43 ( 3 ): 230 - 236 .
Manera A , van der Hagen T H J J . Stability of natural-circulation-cooled boiling water reactors during startup: experimental results [J]. Nuclear Technology , 2003 , 143 ( 1 ): 77 - 88 .
Manera A , Rohde U , Prasser H M , et al . Modeling of flashing-induced instabilities in the start-up phase of natural-circulation BWRs using the two-phase flow code FLOCAL [J]. Nuclear Engineering and Design , 2005 , 235 ( 14 ): 1517 - 1535 .
Bragt D D B V , Kruijf W J M D , Manera A , et al . Analytical modeling of flashing-induced instabilities in a natural circulation cooled boiling water reactor [J]. Nuclear Engineering and Design , 2002 , 215 ( 1/2 ): 87 - 98 .
van der Hagen T H J J , Stekelenburg A J C . The low-power low-pressure flow resonance in a natural circulation cooled boiling water reactor [J]. Nuclear Engineering and Design , 1997 , 177 ( 1/2/3 ): 229 - 238 .
陈景 , 高祖瑛 . 简化沸水堆(SSBWR-200)的热工设计和事故分析 [J]. 清华大学学报(自然科学版) , 2001 , 41 ( 6 ): 52 - 55 .
Chen J , Gao Z Y . Thermal-hydraulic design and accident analysis of small simplified BWR (SSBWR-200) [J]. Journal of Tsinghua University (Science and Technology) , 2001 , 41 ( 6 ): 52 - 55 .
严育华 , 高祖瑛 , 郑文祥 , 等 . 小型热电联供沸水堆CR-200研究 [J]. 清华大学学报 , 1995 , 35 ( 6 ): 83 - 88 .
Yan Y H , Gao Z Y , Zheng W X , et al . Preliminary study on small cogeneration BWR CR-200 [J]. Journal of Tsinghua University , 1995 , 35 ( 6 ): 83 - 88 .
吴莘馨 , 姜胜耀 , 吴少融 , 等 . 喷泉不稳定诱发间歇流量振荡实验研究 [J]. 核动力工程 , 1997 , 18 ( 2 ): 124 - 128 .
Wu X X , Jiang S Y , Wu S R , et al . Experimental investigation on geysering induced intermittent flow oscillation [J]. Nuclear Power Engineering , 1997 , 18 ( 2 ): 124 - 128 .
王建军 , 杨星团 , 姜胜耀 . HRTL-5自然循环稳态特性 [J]. 原子能科学技术 , 2008 , 42 ( 5 ): 434 - 437 .
Wang J J , Yang X T , Jiang S Y . Steady-state behaviors of natural circulation in HRTL-5 [J]. Atomic Energy Science and Technology , 2008 , 42 ( 5 ): 434 - 437 .
Wang J H , Sun Y L , Wang J J , et al . Numerical study of nuclear coupled two-phase flow instability in natural circulation system under low pressure and low quality [J]. Nuclear Engineering & Design , 2011 , 241 ( 12 ): 4972 - 4977 .
Wang J J , Yang X T , Jiang S Y . Simulation of flow excursion and thermal siphon under natural circulation condition with lower pressure and lower quality [J]. Nuclear Power Engineering , 2007 , 2 ( 2 ): 169 - 173 .
Yang X T , Jiang S Y , Zhang Y J . Analysis of characteristic curves for natural circulation flow excursion at low steam quality conditions [J]. Nuclear Power Engineering , 2006 , 27 ( 1 ): 47 - 52 .
Jiang S Y , Wu X X , Zhang Y J . Experimental study of two-phase flow oscillation in natural circulation [J]. Nuclear Science and Engineering , 2000 , 135 ( 2 ): 177 - 189 .
侯晓凡 , 孙中宁 , 范广铭 , 等 . 开式自然循环系统启动特性研究 [J]. 原子能科学技术 , 2015 , 49 ( 10 ): 1772 - 1777 .
Hou X F , Sun Z N , Fan G M , et al . Experimental investigation of startup characteristics in open natural circulation system [J]. Atomic Energy Science and Technology , 2015 , 49 ( 10 ): 1772 - 1777 .
Hou X F , Sun Z N , Su J Q , et al . An investigation on flashing instability induced water hammer in an open natural circulation system [J]. Progress in Nuclear Energy , 2016 , 93 : 418 - 430 .
Guo X Q , Sun Z N , Wang J J , et al . Numerical simulation of the transient behaviors in an open natural circulation system with a large scale [J]. Annals of Nuclear Energy , 2015 , 77 : 83 - 93 .
Bai J H , Zhao B , Wang J J . Study on the performance of an open-loop passive containment cooling system [J]. Journal of Nuclear Science and Technology , 2017 , 55 ( 1 ): 1 - 9 .
Guo X Q , Sun Z N , Wang J J , et al . Simulating investigations on the start-up of the open natural circulation system [J]. Nuclear Engineering and Design , 2015 , 289 : 35 - 48 .
Inada F , Furuya M , Yasuo A . Thermo-hydraulic instability of boiling natural circulation loop induced by flashing (analytical consideration) [J]. Nuclear Engineering and Design , 2000 , 200 ( 1/2 ): 187 - 199 .
朱智强 , 阎昌琪 , 王建军 , 等 . 棒束通道内自然循环流动阻力特性 [J]. 化工学报 , 2018 , 69 ( 4 ): 1398 - 1404 .
Zhu Z Q , Yan C Q , Wang J J , et al . Flow resistance characteristics in rod bundle channel under natural circulation condition [J]. CIESC Journal , 2018 , 69 ( 4 ): 1399 - 1403 .
Tan S C , Su G H , Gao P Z . Experimental study on two-phase flow instability of natural circulation under rolling motion condition [J]. Annals of Nuclear Energy , 2009 , 36 ( 1 ): 103 - 113 .
Zhang W C , Tan S C , Gao P Z , et al . Study on chaotic characteristics of natural circulation flow instability under rolling motion [J]. Atomic Energy Science and Technology , 2012 , 46 ( 6 ): 705 - 709 .
Chen X B , Gao P Z , Tan S C , et al . An experimental investigation of flow boiling instability in a natural circulation loop [J]. International Journal of Heat and Mass Transfer , 2018 , 117 : 1125 - 1134 .
Jain V , Nayak A K , Vijayan P K , et al . Experimental investigation on the flow instability behavior of a multi-channel boiling natural circulation loop at low-pressures [J]. Experimental Thermal and Fluid Science , 2010 , 34 ( 6 ): 776 - 787 .
俞冀阳 , 贾宝山 . 一种反应堆非能动余热排出系统的方案设计 [J]. 核科学与工程 , 2003 , 23 ( 1 ): 32 - 38 .
Yu J Y , Jia B S . Study of one design of passive residual heat removal system of nuclear reactor [J]. Chinese Journal of Nuclear Science and Engineering , 2003 , 23 ( 1 ): 32 - 38 .
俞冀阳 , 俞尔俊 , 贾宝山 . 核反应堆非能动余热排出系统分析 [J]. 核安全 , 2004 , ( 4 ): 35 - 39 .
Yu J Y , Yu E J , Jia B S . Analyses on passive residual heat removal system of nuclear reactors [J]. Nuclear Safety , 2004 , ( 4 ): 35 - 39 .
王飞 , 彭新建 , 杨祖毛 , 等 . 位差对系统自然循环能力的影响实验研究 [J]. 核动力工程 , 2002 , 23 ( 4 ): 25 - 28 .
Wang F , Peng X J , Yang Z M , et al . Experimental investigation of effect of height difference on natural circulation capability [J]. Nuclear Power Engineering , 2002 , 23 ( 4 ): 25 - 28 .
He F , Yang J L , Wang X F . Condensation-induced steam bubble collapse in a pipeline [J]. Tsinghua Science & Technology , 2012 , 5 ( 4 ): 424 - 427 .
Naeeni N , Yaghoubi M . Analysis of wind flow around a parabolic collector (2): Heat transfer from receiver tube [J]. Renewable Energy , 2007 , 32 ( 8 ): 1259 - 1272 .
0
Views
0
下载量
1
CSCD
Publicity Resources
Related Articles
Related Author
Related Institution
京公网安备11010102001995号