Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident

Jun YAO; Xisi ZHANG; Wenjun HU; Xiang CHAI; Yanhua YANG

doi:10.11889/j.0253-3219.2018.hjs.41.020604

您当前的位置：

首页 >

文章列表页 >

Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident
- NUCLEAR TECHNIQUES Vol. 41, Issue 2, Article number: 020604(2018)
- 作者机构：
  
  1.上海交通大学上海 200240
  2.中国原子能科学研究院北京 102413
- 作者简介：
- 基金信息：
- DOI：10.11889/j.0253-3219.2018.hjs.41.020604
  CLC： TL364.4
- Received：01 November 2017，
  
  Revised：20 December 2017，
  
  Published：10 February 2018
- 稿件说明：
移动端阅览
Jun YAO, Xisi ZHANG, Wenjun HU, et al. Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident[J]. Nuclear techniques, 2018, 41(2): 020604
DOI：

Jun YAO, Xisi ZHANG, Wenjun HU, et al. Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident[J]. Nuclear techniques, 2018, 41(2): 020604 DOI： 10.11889/j.0253-3219.2018.hjs.41.020604.

摘要

铅铋冷却快堆是第四代核能系统之一，其具有许多运行与安全性优势。但铅铋冷却快堆在运行过程中，堆芯结构材料会受到铅铋合金冷却剂的腐蚀作用，腐蚀产物在堆内堆积可能会引发堵流事故，从而导致包壳传热恶化，并影响冷却剂的流动传热效果。通过对铅铋冷却快堆单盒燃料组件建模，使用商用计算流体力学软件STAR-CCM+对不同堵块参数下的5个堵流事故工况开展了计算分析。通过对事故后包壳内壁面温度、子通道中心温度的轴向发展和堵块周围流场的轴向速度分布进行对比分析，获得了各种堵块参数对堵流事故后传热恶化、流场性质的不同影响规律。

Abstract

Background

Lead-cooled fast reactor (LFR) is one of six candidates for Generation Ⅳ nuclear systems. Although lead-bismuth eutectic (LBE) has excellent neutron properties

thermal-hydraulic performance and inherent safety features

the structure and cladding materials could be eroded by LBE coolant. The erosion products could accumulate in fuel assembly and grow as a blockage influencing the heat transfer of cladding and coolant.

Purpose

This study aims to investigate the block parameter effect on thermal-hydraulic performance of single fuel assembly in lead-bismuth subcritical reactor under various blockage accidents.

Methods

Based on actual geometry and material properties

modeling of single fuel assembly was established. Five blockage accidents were numerically simulated by the commercial computational fluid dynamics (CFD) software STAR-CCM+ with different block parameters.

Results

Temperature variations along the axial direction of cladding inner face and subchannel center were obtained and compared. Axial velocity distributions around block were analyzed. Influence of block parameters for the coolant backflow and the property of flow fields were achieved.

Conclusion

The maximum temperature rise unanimously occurs inside block. Different block parameters diversely influence flow and heat transfer.

关键词

Keywords

references

OECD/NEA. Technology roadmap update for generation Ⅳ nuclear energy systems[R]. Vienna: IAEA, 2014.

吴宜灿 , FDS团队 . 第四代核能系统铅基反应堆前景展望 . 科技导报 , 2015 . 33 ( 14 ): 12 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=kjdb201514009&dbname=CJFD&dbcode=CJFQ .

Yican WU , FDS Team . Prospect of generation Ⅳ nuclear energy system-lead-based reactor . Science and Technology Review , 2015 . 33 ( 14 ): 12 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=kjdb201514009&dbname=CJFD&dbcode=CJFQ .

W L Huang , R Y Sa , D N Zhou , . Experimental study on fragmentation behaviors of molten LBE and water contact interface . Nuclear Science and Techniques , 2015 . 26 ( 6 ): 060601 DOI: 10.13538/j.1001-8042/nst.26.060601 http://doi.org/10.13538/j.1001-8042/nst.26.060601 .

A E Waltar , D R Todd , P V Tsvetkov . Fast spectrum reactors , Springer US , 2012 . DOI: 10.1007/978-1-4419-9572-8 http://doi.org/10.1007/978-1-4419-9572-8 .

Venneri F, Bowman C, Jameson R. Accelerator-driven transmutation of waste (ATW), a new method for reducing the long-term radioactivity of commercial nuclear waste[A]. Physics World. Bristol: IOP Publishing, 1993.

C F Smith , W G Halsey , N W Brown , . SSTAR:the US lead-cooled fast reactor (LFR) . Journal of Nuclear Materials , 2008 . 376 ( 3 ): 255 - 259 . DOI: 10.1016/j.jnucmat.2008.02.049 http://doi.org/10.1016/j.jnucmat.2008.02.049 .

Wade D C, Feldman E, Sienicki J, et al. ENHS: the encapsulated nuclear heat source-a nuclear energy concept for emerging worldwide energy markets[C]. Tenth International Conference on Nuclear Engineering, Virginia, USA, 2002. DOI: 10.1115/ICONE10-22202. http://dx.doi.org/10.1115/ICONE10-22202.

A Alemberti , V Smirnov , C F Smith , . Overview of lead-cooled fast reactor activities . Progress in Nuclear Energy , 2014 . 77 300 - 307 . DOI: 10.1016/j.pnucene.2013.11.011 http://doi.org/10.1016/j.pnucene.2013.11.011 .

H A Abderrahim , P D'hondt . MYRRHA:a European experimental ADS for R & D applications status at Mid-2005 and prospective towards implementation . Journal of Nuclear Science & Technology , 2007 . 44 ( 3 ): 491 - 498 . DOI: 10.1080/18811248.2007.9711313 http://doi.org/10.1080/18811248.2007.9711313 .

Frogheri M, Alemberti A, Mansani L. The lead fast reactor: demonstrator (ALFRED) and ELFR design[C]. International Conference on FAST Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, Paris, France, 2013. https: //www. researchgate. net/publication/264422690_The_Lead_Fast_Reactor_Demonstrator_ALFRED_And_ELFR_Design

Sekimoto H, Makino S, Nakamura K, et al. LBE-cooled long-life safe simple small portable proliferation-resistant reactor (LSPR)[C]. Japan-Russia LBE Coolant Workshop, Tokyo, Japan, 2001.

M Takahashi , S Uchida , Y Kasahara . Design study on reactor structure of Pb-Bi-cooled direct contact boiling water fast reactor (PBWFR) . Progress in Nuclear Energy , 2008 . 50 ( 2 ): 197 - 205 . DOI: 10.1016/j.pnucene.2007.10.026 http://doi.org/10.1016/j.pnucene.2007.10.026 .

袁显宝 , 曹良志 , 吴宏春 . 铅铋冷却氮化物燃料小型模块化快中子反应堆堆芯物理特性分析 . 核技术 , 2017 . 40 ( 10 ): 100603 DOI: 10.11889/j.0253-3219.2017.hjs.40.100603 http://doi.org/10.11889/j.0253-3219.2017.hjs.40.100603 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract829.shtml .

Xianbao YUAN , Liangzhi CAO , Hongchun WU . Physical characteristics of small modular Pb-Bi cooled reactor with nitride nuclear fuel . Nuclear Techniques , 2017 . 40 ( 10 ): 100603 DOI: 10.11889/j.0253-3219.2017.hjs.40.100603 http://doi.org/10.11889/j.0253-3219.2017.hjs.40.100603 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract829.shtml .

霍启军 , 周涛 , 李云博 , . 铅铋合金自然循环稳定流动的析因分析 . 核技术 , 2015 . 38 ( 3 ): 030604 DOI: 10.11889/j.0253-3219.2015.hjs.38.030604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.030604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract372.shtml .

Qijun HUO , Tao ZHOU , Yunbo LI , . Steady flow research of lead bismuth eutectic under natural circulation based on factorial analysis . Nuclear Techniques , 2015 . 38 ( 3 ): 030604 DOI: 10.11889/j.0253-3219.2015.hjs.38.030604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.030604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract372.shtml .

龚昊. 铅铋冷却快堆单盒组件堵流事故分析研究[D]. 合肥: 中国科学技术大学, 2014. http: //cdmd. cnki. com. cn/Article/CDMD-10358-1014299687. htm

GONG Hao. Analysis of blockage accident for single assembly of LBE-cooled fast reactor[D]. Hefei: University of Science and Technology of China, 2014.

K Morita , W Maschek , M Flad , . Thermodynamic properties of lead-bismuth eutectic for use in reactor safety analysis . Journal of Nuclear Science & Technology , 2006 . 43 ( 5 ): 526 - 536 . DOI: 10.1080/18811248.2006.9711131 http://doi.org/10.1080/18811248.2006.9711131 .

R N Lyon , D L V Katz . Liquid-metals handbook , : Washington U.S. Government Printing Office , 1952 .

苏子威 , 周涛 , 刘梦影 , . 液态铅铋合金热物性研究 . 核技术 , 2013 . 36 ( 9 ): 090205 DOI: 10.11889/j.0253-3219.2013.hjs.36.090205 http://doi.org/10.11889/j.0253-3219.2013.hjs.36.090205 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract75.shtml .

Ziwei SU , Tao ZHOU , Mengying LIU , . Thermophysical properties of liquid lead-bismuth eutetic . Nuclear Techniques , 2013 . 36 ( 9 ): 090205 DOI: 10.11889/j.0253-3219.2013.hjs.36.090205 http://doi.org/10.11889/j.0253-3219.2013.hjs.36.090205 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract75.shtml .

S S Kutateladze . Liquid metal heat transfer media , : New York Comsultants Bureau Inc , 1959 .

R R Hultgren . Selected values of the thermodynamic properties of binary alloys , : Washington American Society for Metals , 1973 .

T Lida , R I L Guthrie . The physical properties of liquid metals , Oxford University Press , 1988 .

Y S Touloukian . Thermophysical properties of matter , IFI/Plenum , 1970 .

J Pacio , M Daubner , F Fellmoser , . Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers . Nuclear Engineering & Design , 2014 . 273 33 - 46 . DOI: 10.1016/j.nucengdes.2014.02.020 http://doi.org/10.1016/j.nucengdes.2014.02.020 .

C Li , S M Ji , D P Tan . Softness abrasive flow method oriented to tiny scale mold structural surface . International Journal of Advanced Manufacturing Technology , 2012 . 61 ( 9-12 ): 975 - 987 . DOI: 10.1007/s00170-011-3621-y http://doi.org/10.1007/s00170-011-3621-y .

Views

下载量

CSCD

Alert me when the article has been cited

提交

Tools

Publicity Resources

Study on the influence of novel mixing vanes on fretting wear caused by fuel rods flow-induced vibration

Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies

CFD based study of natural convection characteristics driven by buoyancy in containment

Analysis and optimization of flow distribution for the reactor core of China initiative accelerator driven system

Uncertainty quantification study of CFD on the rod bundle flow

Related Author

HE Hui

LIU Xiaojing

CHAI Xiang

YUAN Shuo

ZHANG Yaoli

HONG Gang

YAO Jiaye

LU Jiaming

Related Institution

Shanghai Digital Nuclear Reactor Technology Intergration Innovation Center

School of Mechanical and Power Engineering, Shanghai Jiaotong University

Country College of Smart Energy, Shanghai Jiaotong University

College of Energy, Xiamen University

China Electric Power Research Institute

AI问答

Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
Tel：021-39194977 Email：LHB@sinap.ac.cn
Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1 京公网安备11010802024621
It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
Total Visits：880473

⁰