不同燃料球排布方式下熔盐堆堆芯流动和换热特性研究

靖剑平; 贾斌; 雷蕾; 毕金生; 左嘉旭; 刘雅宁; 张春明; 张大林

doi:10.11889/j.0253-3219.2017.hjs.40.020602

您当前的位置：

首页 >

文章列表页 >

不同燃料球排布方式下熔盐堆堆芯流动和换热特性研究

核能科学与工程 | 更新时间：2021-05-19

- 不同燃料球排布方式下熔盐堆堆芯流动和换热特性研究
- Characteristic of core flow and heat transfer of different fuel ball arrangement modes in molten salt reactor
- 核技术 2017年40卷第2期文章编号：020602
- 作者机构：
  
  1.环境保护部核与辐射安全中心北京 100082
  2.中国科学院过程工程研究所多相复杂系统国家重点实验室北京 100190
  3.西安交通大学核能科学与技术学院西安 710049
- 作者简介：
  
  [ "靖剑平, 男, 1983年出生, 2010年于哈尔滨工业大学获博士学位, 研究领域为反应堆热工水力及安全分析", "JING Jianping, male, born in 1983, graduated from Harbin Institute of Technology with a doctoral degree in 2010, focusing on the reactor thermal hydraulic and safety analysis" ]
  刘雅宁, E-mail:ynliu@ipe.ac.cn LIU Yaning, E-mail:ynliu@ipe.ac.cn
- 基金信息：
  
  中国科学院战略性先导科技专项(XDA02050500);国家自然科学基金(11505076);国家自然科学基金(21306201)
- DOI：10.11889/j.0253-3219.2017.hjs.40.020602
  中图分类号： TL99
- 收稿日期：2016-11-21，
  
  修回日期：2016-12-13，
  
  纸质出版日期：2017-02-10
- 稿件说明：
移动端阅览
靖剑平, 贾斌, 雷蕾, 等. 不同燃料球排布方式下熔盐堆堆芯流动和换热特性研究[J]. 核技术, 2017,40(2):020602

Jianping JING, Bin JIA, Lei LEI, et al. Characteristic of core flow and heat transfer of different fuel ball arrangement modes in molten salt reactor[J]. Nuclear techniques, 2017, 40(2): 020602
靖剑平, 贾斌, 雷蕾, 等. 不同燃料球排布方式下熔盐堆堆芯流动和换热特性研究[J]. 核技术, 2017,40(2):020602 DOI： 10.11889/j.0253-3219.2017.hjs.40.020602.

Jianping JING, Bin JIA, Lei LEI, et al. Characteristic of core flow and heat transfer of different fuel ball arrangement modes in molten salt reactor[J]. Nuclear techniques, 2017, 40(2): 020602 DOI： 10.11889/j.0253-3219.2017.hjs.40.020602.

摘要

固态燃料熔盐堆（Thorium Molten Salt Reactor-Solid Fuel，TMSR-SF）的堆芯是由燃料石墨球随机堆积而成的，在分析中建立随机堆积的小球模型存在较大困难和不确定性，通常假设为规则的排布方式。利用计算流体力学分析程序，选取了面心立方和体心立方两种规则的小球排布方式进行建模，分析不同排布方式下堆芯流动和换热的特性。结果表明，面心立方排布下的流线呈现出周期性弯曲，小球中心最高温度为1153 K，总压降为1323 Pa，体心立方排布下的流线大体呈直线，小球中心最高温度为1155 K，总压降为574 Pa，面心立方排布的流动压降明显大于体心立方排布。对于单个中间小球，面心立方排布的小球表面温度分布更均匀，热点温度更低，但熔盐从燃料球底部流动到顶部的压降更大。

Abstract

Background

Thorium-based molten salt reactor nuclear power system project is one of the leading science and technology projects of Chinese Academy of Sciences

its strategic goal is to develop the fourth generation fission reactor nuclear power system. The core of solid fuel molten salt reactor is constructed of the random pileup of fuel graphite balls

which brings difficulties and uncertainties in the establishment of the pebble bed model for simulation analysis.

Purpose

This study aims to analyze the influence of two modes of fuel ball arrangement on the core flow and heat transfer in the molten salt reactor

which are face centered cubic (FCC) and body centered cubic (BCC) arrangement mode.

Methods

Based on the computational fluid dynamics (CFD) program

two computational models based on the FCC and BCC arrangement modes are established respectively. The re-normalization group (RNG)

k-ε

turbulence model is selected with constant velocity and temperature as the inlet boundary conditions and constant pressure as the outlet boundary condition whilst the gauge pressure is assumed to be zero.

Results

Compared to the BCC arrangement mode

the streamline under the FCC arrangement mode is more complex

the flow pressure drop is larger

the fuel ball surface temperature distribution is more uniform

and the hot spot temperature is lower. Under the FCC arrangement mode

the maximum temperature of the ball center is 1153 K

the total pressure drop is 1323 Pa; under the BCC arrangement mode

the maximum temperature of the ball center is 1155 K

the total pressure drop is 574 Pa.

Conclusion

The streamlines under the FCC arrangement mode are periodically curved and the streamlines under the BCC arrangement mode are generally straight. Under FCC arrangement mode

the surface temperature distribution of a single intermediate fuel ball is more uniform and the hot spot temperature is lower

but the pressure drop from the bottom of the fuel ball to the top is larger than that of BCC arrangement mode.

关键词

Keywords

references

李华 , 秋穗正 , 苏光辉 , . 球床堆内冷却剂流动与传热特性的CFD研究 . 核动力工程 , 2009 . 30 ( S1 ): 39 - 43 . DOI: 10.7538/yzk.2009.39.5S1.0039 http://doi.org/10.7538/yzk.2009.39.5S1.0039 .

Hua LI , Suizheng QIU , Guanghui SU , . CFD research on flow and heat transfer characteristics of coolant in pebble bed reactor core . Nuclear Power Engineering , 2009 . 30 ( S1 ): 39 - 43 . DOI: 10.7538/yzk.2009.39.5S1.0039 http://doi.org/10.7538/yzk.2009.39.5S1.0039 .

李健 , 宋小明 , 鲁剑超 , . 基于有序堆积球床的单相阻力特性实验研究与数值模拟 . 原子能科学与技术 , 2012 . 46 ( S1 ): 807 - 810 . DOI: 10.13832/j.jnpe.2012.S1.0807 http://doi.org/10.13832/j.jnpe.2012.S1.0807 .

Jian LI , Xiaoming SONG , Jianchao LU , . Experimental research and numerical simulation on single phase flow resistance characteristics of orderly packed bed . Atomic Energy Science and Technology , 2012 . 46 ( S1 ): 807 - 810 . DOI: 10.13832/j.jnpe.2012.S1.0807 http://doi.org/10.13832/j.jnpe.2012.S1.0807 .

潘登 , 余笑寒 , 邹杨 , . 规则球床堆熔盐流动压降与对流换热CFD模拟 . 核技术 , 2016 . 39 ( 8 ): 080604 DOI: 10.11889/j.0253-3219.2016.hjs.39.080604 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.080604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract624.shtml .

Deng PAN , Xiaohan YU , Yang ZOU , . CFD-simulation of structured packed beds molten salt reactors on pressure drop and heat transfer . Nuclear Techniques , 2016 . 39 ( 8 ): 080604 DOI: 10.11889/j.0253-3219.2016.hjs.39.080604 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.080604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract624.shtml .

S X Song , X Z Cai , Y F Liu , . Pore scale thermal hydraulics investigations of molten salt cooled pebble bed high temperature reactor with BCC and FCC configurations . Science and Technology of Nuclear Installations , 2014 . ( 3 ): 1 - 16 . DOI: 10.1155/2014/589895 http://doi.org/10.1155/2014/589895 .

焦小伟 , 王凯 , 何兆忠 , . 固态熔盐堆全厂断电ATWS事故工况下的堆芯安全探讨 . 核技术 , 2015 . 38 ( 2 ): 020604 DOI: 10.11889/j.0253-3219.2015.hjs.38.020604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract358.shtml .

Xiaowei JIAO , Kai WANG , Zhaozhong HE , . Core safety discussion under station blackout ATWS accident of solid fuel molten salt reactor . Nuclear Techniques , 2015 . 38 ( 2 ): 020604 DOI: 10.11889/j.0253-3219.2015.hjs.38.020604 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.020604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract358.shtml .

TMSR-SFl堆物理分总体. 10 MWt TMSR-SFl总体物理方案和参数[R].上海:中国科学院上海应用物理研究所, 2013.

Reactor Physics Department of TMSR-SF1.Physics programs and parameters for 10-MWt TMSR-SF1[R]. Shanghai: Shanghai Institute of Applied Physics, Chinese Academy of Sciences, 2013.

梅牡丹 , 邵世威 , 何兆忠 , . 固态钍基熔盐堆概率安全评价始发事件分析研究 . 核技术 , 2014 . 37 ( 9 ): 090601 DOI: 10.11889/j.0253-3219.2014.hjs.37.090601 http://doi.org/10.11889/j.0253-3219.2014.hjs.37.090601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract260.shtml .

Mudan MEI , Shiwei SHAO , Zhaozhong HE , . Research on initial event analysis for solid thorium molten salt reactor probabilistic safety assessment . Nuclear Techniques , 2014 . 37 ( 9 ): 090601 DOI: 10.11889/j.0253-3219.2014.hjs.37.090601 http://doi.org/10.11889/j.0253-3219.2014.hjs.37.090601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract260.shtml .

靖剑平 , 刘雅宁 , 贾斌 , . 10 MWt固态燃料熔盐堆控制棒失控抽出事故分析 . 核技术 , 2016 . 39 ( 10 ): 100604 DOI: 10.11889/j.0253-3219.2016.hjs.39.100604 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.100604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract664.shtml .

Jianping JING , Yaning LIU , Bin JIA , . Accident analyses of uncontrolled rod cluster control assembly bank withdrawal for 10-MWt thorium-based molten salt reactor-solid fuel . Nuclear Techniques , 2016 . 39 ( 10 ): 100604 DOI: 10.11889/j.0253-3219.2016.hjs.39.100604 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.100604 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract664.shtml .

L M Liu , D L Zhang , Q Lu , . Preliminary neutronic and thermal-hydraulic analysis of a 2-MW thorium-based molten salt reactor with solid fuel . Progress in Nuclear Energy , 2016 . 86 1 - 10 . DOI: 10.1016/j.pnucene.2015.09.011 http://doi.org/10.1016/j.pnucene.2015.09.011 .

牛强 , 宋士雄 , 魏泉 , . 熔盐冷却球床堆热通道热工水力特性数值分析 . 核技术 , 2014 . 37 ( 7 ): 070602 DOI: 10.11889/j.0253-3219.2014.hjs.37.070602 http://doi.org/10.11889/j.0253-3219.2014.hjs.37.070602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract239.shtml .

Qiang NIU , Shixiong SONG , Quan WEI , . Thermal-hydraulics numerical analyses of pebble bed advanced high temperature reactor hot channel . Nuclear Techniques , 2014 . 37 ( 7 ): 070602 DOI: 10.11889/j.0253-3219.2014.hjs.37.070602 http://doi.org/10.11889/j.0253-3219.2014.hjs.37.070602 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract239.shtml .

浏览量

下载量

CSCD

文章被引用时，请邮件提醒。

提交

工具集

关联资源

新型搅混翼对燃料棒流致振动导致的微动磨蚀影响研究

铅铋堆燃料组件子通道计算方法优化

基于CFD的安全壳内浮力驱动自然对流特性分析

中国加速器驱动嬗变研究装置堆芯流量分配设计与优化

棒束单相流动CFD的不确定性量化研究