Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet

Quansheng FENG; Bo XU; Deng PAN; Yang ZOU; Hongjie XU

doi:10.11889/j.0253-3219.2017.hjs.40.090601

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Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet

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

- Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet
  封面论文
- NUCLEAR TECHNIQUES Vol. 40, Issue 9, Article number: 090601(2017)
- 作者机构：
  
  1.中国科学院上海应用物理研究所嘉定园区上海 201800
  2.中国科学院大学北京 100049
  3.核动力运行研究所武汉 430223
- 作者简介：
- 基金信息：
  
  Strategic Priority Program of Chinese Academy of Sciences
- DOI：10.11889/j.0253-3219.2017.hjs.40.090601
  CLC： TL33
- Received：04 November 2016，
  
  Revised：13 April 2017，
  
  Published：2017-09
- 稿件说明：
移动端阅览
Quansheng FENG, Bo XU, Deng PAN, et al. Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet[J]. Nuclear techniques, 2017, 40(9): 090601
DOI：

Quansheng FENG, Bo XU, Deng PAN, et al. Thermal-hydraulics numerical analyses of molten salt pebble-bed reactor core inlet[J]. Nuclear techniques, 2017, 40(9): 090601 DOI： 10.11889/j.0253-3219.2017.hjs.40.090601.

摘要

堆芯入口流场设计是小型固态燃料熔盐堆系统项目内容之一，它对反应堆结构的稳定性、堆芯温度和流场分布有着非常重要的影响。研究了熔盐流道流通面积变化对堆芯入口温度、流场分布及压降的影响，优化熔盐流道几何结构。以小型熔盐球床堆模型为研究对象，取符合实际边界条件的输入参数，通过改变熔盐流道流通面积，使用计算流体力学（Computational Fluid Dynamics，CFD）通用程序Fluent 16.0对堆芯入口内熔盐的热工水力特性进行数值模拟。在考虑实际下反射层流道的流通面积占比最大为18.14%下，研究了熔盐流道流通面积占比在区间[0，15.00%]变化。结果表明，堆芯活性区熔盐最高局部热点温度随熔盐流道流通面积比的增大而增高；堆芯入口内的压降随下反射层熔盐流道流通面积比的减小而增大；在径向方向上流进孔道的熔盐流速随着孔道远离堆芯位置而增大。本研究可为小型固态燃料球床熔盐堆优化设计提供一定的参考价值。

Abstract

Background:

The flow field design at the core inlet has a particularly important influence on structure stability

temperature distribution and flow field of a small solid fuel salt reactor system.

Purpose:

This study aims to optimize the flow channel structure by analyzing the effect of the thermal-hydraulic characteristics.

Methods:

Base on the design of a small molten salt pebble-bed reactor

input parameters of the practical boundary conditions were adopted for simulation study using Fluent 16.0 of computational fluid dynamics (CFD).Thermal-hydraulic characteristics such as temperature field

flow field and pressure drop

of core inlet were simulated through changing the flow areas.

Results:

The computational results showed that when proportion of the flow area was in the range of[0

15.00%]

the maximum local temperature in the active core region increased and the pressure drop in the core inlet decreased with the increase of the flow area.As the channel is far away from the core position

salt velocity increases gradually along the radial direction.

Conclusion:

The numerical results provide a useful proposal to optimize the design of a small solid fuel salt reactor.

关键词

Keywords

references

江绵恒 , 徐洪杰 , 戴志敏 . 未来先进核裂变能——TMSR核能系统 . 中国科学院院刊 , 2012 . 27 ( 3 ): 366 - 374 . DOI: 10.3969/j.issn.1000-3045.2012.03.016 http://doi.org/10.3969/j.issn.1000-3045.2012.03.016 .

Mianheng JIANG , Hongjie XU , Zhimin DAI . Advanced fission energy program-TMSR nuclear energy system . Bulletin of Chinese Academy of Sciences , 2012 . 27 ( 3 ): 366 - 374 . DOI: 10.3969/j.issn.1000-3045.2012.03.016 http://doi.org/10.3969/j.issn.1000-3045.2012.03.016 .

刘兴民 , 陆道纲 , 刘天才 , . 中国先进研究堆堆芯流量分配的数值模拟 . 核动力工程 , 2003 . 24 ( S6 ): 21 - 24 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG2003S2005.htm .

Xingmin LIU , Daogang LU , Tiancai LIU , . Numerical simulation of core flow distribution for China advanced research reactor . Nuclear Power Engineering , 2003 . 24 ( S6 ): 21 - 24 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG2003S2005.htm .

G H Lee , Y S Bang , S W Woo , . A numerical study for the effect of flow skirt geometry on reactor internal flow . Annals of Nuclear Energy , 2013 . 62 452 - 462 . DOI: 10.1016/j.anucene.2013.07.005 http://doi.org/10.1016/j.anucene.2013.07.005 .

俞冀阳 , 贾宝山 . 反应堆热工水力学 , : 北京清华大学出版社 , 2011 .

Jiyang YU , Baoshan JIA . Reactor thermal hydraulics , : Beijing Tsinghua University Press , 2011 .

宋士雄 , 魏泉 , 蔡翔舟 , . 基于CFD方法的球床式高温气冷堆稳态热工水力分析 . 核技术 , 2013 . 36 ( 12 ): 120601 DOI: 10.11889/j.0253-3219.2013.hjs.36.120601 http://doi.org/10.11889/j.0253-3219.2013.hjs.36.120601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract117.shtml .

Shixiong SONG , Quan WEI , Xiangzhou CAI , . High temperature gas-cooled pebble bed reactor steady state thermal-hydraulics analyses based on CFD method . Nuclear Techniques , 2013 . 36 ( 12 ): 120601 DOI: 10.11889/j.0253-3219.2013.hjs.36.120601 http://doi.org/10.11889/j.0253-3219.2013.hjs.36.120601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract117.shtml .

闫晓 , 肖泽军 , 黄彦平 , . 多孔介质中流动换热特性的研究进展 . 核动力工程 , 2006 . 27 ( 1 ): 78 - 82 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG2006S1017.htm .

Xiao YAN , Zejun XIAO , Yanping HUANG , . Research progress on flow and heat transfer in porous media . Nuclear Power Engineering , 2006 . 27 ( 1 ): 78 - 82 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG2006S1017.htm .

张宏亮 , 刘海鹏 , 方才顺 , . 反应堆下腔室结构优化设计 . 核动力工程 , 2014 . 35 ( 3 ): 59 - 63 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG201403014.htm .

Hongliang ZHANG , Haipeng LIU , Caishun FANG , . Optimization design of reactor lower plenum . Nuclear Power Engineering , 2014 . 35 ( 3 ): 59 - 63 . http://www.cnki.com.cn/Article/CJFDTOTAL-HDLG201403014.htm .

J H Jeong , B S Han . Coolant flow field in a real geometry of PWR downcomer and lower plenum . Annals of Nuclear Energy , 2008 . 35 ( 4 ): 610 - 619 . DOI: 10.1016/j.anucene.2007.08.010 http://doi.org/10.1016/j.anucene.2007.08.010 .

P N Haubenreich , J R Engel . Experience with the molten salt reactor experiment . Nuclear Applications and Technology , 1970 . 8 118 - 136 . DOI: 10.13182/NT8-2-118 http://doi.org/10.13182/NT8-2-118 .

Arlemark E. CFD model of fluid flow in reactor:a simulation of velocity and heat distribution in a channel[D]. Piscataway, USA:Department of Physics and Astronomy, 2006.

M Kao , C Y Wu , C C Chieng , . CFD analysis of PWR core top and reactor vessel upper plenum internals subdomain models . Nuclear Engineering and Design , 2011 . 241 ( 10 ): 4181 - 4193 . DOI: 10.1016/j.nucengdes.2011.08.007 http://doi.org/10.1016/j.nucengdes.2011.08.007 .

S Becker , E Laurien . Three-dimensional numerical simulation of flow and heat transport in high-temperature nuclear reactors . Nuclear Engineering and Design , 2003 . 222 189 - 201 . DOI: 10.1016/S0029-5493(03)00011-6 http://doi.org/10.1016/S0029-5493(03)00011-6 .

罗磊 , 陈文振 , 郝建立 , . 压水堆下腔室流场对堆芯流场和温度场影响数值分析 . 原子能科学技术 , 2012 . 46 ( S1 ): 236 - 239 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2012S1051.htm .

Lei LUO , Wenzhen CHEN , Jianli HAO , . Numerical analysis on mass flow rate distribution of PWR lower plemum . Atomic Energy Science and Technology , 2012 . 46 ( S1 ): 236 - 239 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2012S1051.htm .

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