

浏览全部资源
扫码关注微信
南华大学 核科学技术学院 衡阳 421001
Received:09 January 2017,
Revised:21 February 2017,
Published:10 May 2017
移动端阅览
Hui CHEN, Wenjie ZENG, Dongnan ZHANG, et al. Analysis of jet device transient feature during start-up period of primary pump[J]. Nuclear techniques, 2017, 40(5): 050602
Hui CHEN, Wenjie ZENG, Dongnan ZHANG, et al. Analysis of jet device transient feature during start-up period of primary pump[J]. Nuclear techniques, 2017, 40(5): 050602 DOI: 10.11889/j.0253-3219.2017.hjs.40.050602.
射流装置由射流泵和主泵组成,引入MRX(Marine Reactor X)压水堆一回路系统中,有助于提升反应堆的固有安全性。反应堆启泵过程中,流量急剧上升导致堆芯温度变化,影响堆芯运行安全。通过计算流体力学(Computational Fluid Dynamics,CFD)方法对引入射流装置MRX一回路10%满功率(Full Power,FP)、17.5% FP和25% FP堆芯功率下启泵进行三维瞬态模拟,分析MRX一回路中射流装置流场瞬态特性。结果表明,射流装置的加入可以改善一回路自然循环能力,提高启泵工况下冷却剂初始变化流量,减缓变化趋势,改善过渡安全性;启泵过程中一回路温度存在波动现象,且堆芯功率越大,波动幅度越大,时间越长;启泵完成后射流泵喷嘴处流速较大。验证了压水堆中引入射流装置提升反应堆固有安全性的可行性,同时为进一步优化设计方案提供方向参考。
Background
2
The jet device composed of jet pump and primary pump has the advantages of simple structure and high reliability
and it is suitable for the special environment
such as radioactive
flammable and explosive. It is helpful to improve the inherent safety of the reactor by introducing the jet device as primary pump for Marine Reactor X (MRX). The sudden increase of the coolant flow rate of the reactor leads to the change of the core temperature during start-up period
which affects the safety of the core operation. Purpose:This study aims to obtain the jet device transient feature during start-up period of primary pump in the MRX which introducing the jet device as primary pump.
Methods
2
The primary loop circuit system is modeled with a 3-dimensional (3D) Computational Fluid Dynamics (CFD) code FLUENT
and transient characteristics at 10% full power (FP)
17.5% FP and 25% FP core power conditions were analyzed during the stage of primary pump startup.
Results
2
The analysis results show that the jet device can effectively improve the natural circulation ability of the primary loop circuit system
reform the initial flow rate and slow down the trend of coolant temperature change during start-up period of primary pump
so it can improve the safety of the transition. On the other hand
there are some unfavorable factors of reactor safety during start-up period of primary pump
such as the temperature of the primary circuit fluctuates (the greater the core power
the greater the fluctuation range) and the high flow rate of jet pump.
Conclusion
2
The design of jet device is feasible to improve the safety of MRX
but the real use also needs some adjustment.
何 培杰 , 吕 俊贤 , 龙 新平 , . 喷射泵内部流动数值分析 . 核动力工程 , 2005 . 26 ( 2 ): 135 - 139 . DOI: 10.3969/j.issn.0258-0926.2005.02.009 http://doi.org/10.3969/j.issn.0258-0926.2005.02.009 .
Peijie HE , Junxian LYU , Xinping LONG , . Numerical analysis on flows in jet pumps . Nuclear Power Engineering , 2005 . 26 ( 2 ): 135 - 139 . DOI: 10.3969/j.issn.0258-0926.2005.02.009 http://doi.org/10.3969/j.issn.0258-0926.2005.02.009 .
J Ortiz . BWR online monitoring system based on noise analysis . Nuclear Engineering & Design , 2006 . 236 ( 22 ): 2394 - 2404 . DOI: 10.1016/j.nucengdes.2006.02.009 http://doi.org/10.1016/j.nucengdes.2006.02.009 .
赵 雪岑 , 王 金涛 , 刘 松亚 , . 射流泵水力特性优化设计研究 . 核动力工程 , 2014 . 35 ( 4 ): 129 - 132 . DOI: 10.13832/j.jnpe.2014.04.0129 http://doi.org/10.13832/j.jnpe.2014.04.0129 .
Xuecen ZHAO , Jintao WANG , Songya LIU , . Research of optimization design of jet pump's hydraulic characteristics . Nuclear Power Engineering , 2014 . 35 ( 4 ): 129 - 132 . DOI: 10.13832/j.jnpe.2014.04.0129 http://doi.org/10.13832/j.jnpe.2014.04.0129 .
龙 新平 , 王 丰景 , 俞 志君 . 喷射泵内部流动模拟与其扩散角优化 . 核动力工程 , 2011 . 32 ( 1 ): 53 - 57 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG201101013.htm .
Xinping LONG , Fengjing WANG , Zhijun YU . Optimization of divergence angle of jet pump based on numerical simulation of interior flow field . Nuclear Power Engineering , 2011 . 32 ( 1 ): 53 - 57 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG201101013.htm .
A Mangialardo , W Borreani , G Lomonaco , . Numerical investigation on a jet pump evolving liquid lead for GEN-IV reactors . Nuclear Engineering & Design , 2014 . 28 ( 9 ): 608 - 618 . DOI: 10.1016/j.nucengdes.2014.09.028 http://doi.org/10.1016/j.nucengdes.2014.09.028 .
李 忠朋 , 史 重淼 . 带喷射泵系统中自然循环过渡特性实验研究 . 核动力工程 , 1995 . 16 ( 4 ): 322 - 325 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG504.006.htm .
Zhongpeng LI , Chongmiao SHI . An experiment investigation of natural circulation transient behaviours in a loop with jet pump . Nuclear Power Engineering , 1995 . 16 ( 4 ): 322 - 325 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG504.006.htm .
郝 亚雷 , 于 雷 , 蔡 章生 , . 核动力装置强迫循环与自然循环过渡过程特性研究 . 核科学与工程 , 2007 . 27 ( 1 ): 20 - 26 . DOI: 10.3321/j.issn:0258-0918.2007.01.005 http://doi.org/10.3321/j.issn:0258-0918.2007.01.005 .
Yalei HAO , Lei YU , Zhangsheng CAI , . Study on operation characteristics of natural circulation and forced circulation in nuclear power plant . Nuclear Science and Engineering , 2007 . 27 ( 1 ): 20 - 26 . DOI: 10.3321/j.issn:0258-0918.2007.01.005 http://doi.org/10.3321/j.issn:0258-0918.2007.01.005 .
姚 青生 , 王 章立 , 韩 伟实 , . 自然循环向强迫循环过渡时的反应性变化 . 核动力工程 , 2008 . 29 ( 3 ): 18 - 22 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200803005.htm .
Qingsheng YAO , Zhangli WANG , Weishi HAN , . Transitional reactivity variation from natural to forced circulation . Nuclear Power Engineering , 2008 . 29 ( 3 ): 18 - 22 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG200803005.htm .
陈 森 , 刘 余 , 田 茂林 , . 基于多孔介质模型的压水堆堆芯温场数值模拟 . 核技术 , 2015 . 38 ( 9 ): 090601 DOI: 10.11889/j.0253-3219.2015.hjs.38.090601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.090601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract478.shtml .
Sen CHEN , Yu LIU , Maolin TIAN , . PWR core transient temperature numerical simulation based on porous media model . Nuclear Techniques , 2015 . 38 ( 9 ): 090601 DOI: 10.11889/j.0253-3219.2015.hjs.38.090601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.090601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract478.shtml .
H Gao , F Gao , X C Zhao , . Analysis of reactor coolant pump transient performance in primary coolant system during start-up period . Annals of Nuclear Energy , 2013 . 54 ( 54 ): 202 - 208 . DOI: 10.1016/j.anucene.2012.11.020 http://doi.org/10.1016/j.anucene.2012.11.020 .
汪 胜国 . 日本改进型船用堆MRX概念设计综述 . 核动力工程 , 1995 . 16 ( 3 ): 209 - 217 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG503.003.htm .
Shengguo WANG . Conceptul design report on advanced marine reactor MRX of Japan . Nuclear Power Engineering , 1995 . 16 ( 3 ): 209 - 217 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG503.003.htm .
0
Views
22
下载量
0
CSCD
Publicity Resources
Related Articles
Related Author
Related Institution
京公网安备11010802024621