多工况下CFETR包层背板及流道热工分析

吴琪刚; 刘素梅; 雷明准; 徐坤; 黄卫

doi:10.11889/j.0253-3219.2019.hjs.42.090602

您当前的位置：

首页 >

文章列表页 >

多工况下CFETR包层背板及流道热工分析

核能科学与工程 | 更新时间：2024-10-25

- 多工况下CFETR包层背板及流道热工分析
- Thermal analysis of CFETR blanket back supporting structure and channels under multiple operating conditions
- 核技术 2019年42卷第9期文章编号：090602
- 作者机构：
  
  1.安徽理工大学机械工程学院淮南 232000
  2.中国科学院等离子体物理研究所合肥 230031
- 作者简介：
  
  吴琪刚，男，1995年出生，2017年毕业于安徽科技学院，现为硕士研究生，研究领域为机械CAD/CAE
- 基金信息：
  
  中国聚变工程实验堆集成工程设计研究项目(2017YFE0300500)
- DOI：10.11889/j.0253-3219.2019.hjs.42.090602
  中图分类号： TL62
- 收稿日期：2019-06-04，
  
  修回日期：2019-08-18，
  
  纸质出版日期：2019-09-10
- 稿件说明：
移动端阅览
吴琪刚,刘素梅,雷明准等.多工况下CFETR包层背板及流道热工分析[J].核技术,2019,42(09):73-80.

WU Qigang,LIU Sumei,LEI Mingzhun,et al.Thermal analysis of CFETR blanket back supporting structure and channels under multiple operating conditions[J].NUCLEAR TECHNIQUES,2019,42(09):73-80.
吴琪刚,刘素梅,雷明准等.多工况下CFETR包层背板及流道热工分析[J].核技术,2019,42(09):73-80. DOI： 10.11889/j.0253-3219.2019.hjs.42.090602.

WU Qigang,LIU Sumei,LEI Mingzhun,et al.Thermal analysis of CFETR blanket back supporting structure and channels under multiple operating conditions[J].NUCLEAR TECHNIQUES,2019,42(09):73-80. DOI： 10.11889/j.0253-3219.2019.hjs.42.090602.

摘要

根据中国聚变工程实验堆(China Fusion Engineering Test Reactor

CFETR)包层背板的设计方案及具体的包层模块内部工况，分别完成了对高场侧包层背板和低场侧包层背板的流道的设计。背板的内部流道具体包括两根吹扫气体流道、三根冷却剂冷流道、三根冷却剂热流道。通过ANSYS软件中的FLUENT模块来初步模拟仿真包层背板的固体和流体热工基本情况，分别得到了背板在200 MW、500 MW、1 GW和1.5 GW工况下的温度场分布及各流道内部流体的热交换情况。结果表明：高场侧背板和低场侧背板的最高温度均小于结构材料的许用温度；高场侧和低场侧内部流道的冷却剂平均温度变化均符合包层端入口和出口的设计要求。

Abstract

Background

Blanket is an important component of China fusion engineering test reactor (CFETR). A large amount of heat inside the blanket needs to bring coolant to the outside of the Tokamak device.

Purpose

This study aims to design the channel of inboard (IB) and outboard (OB) back supporting structure (BSS) to suitable for multiple operating conditions.

Methods

The thermal analyses for BSS under four working conditions were performed by FLUENT

a computational fluid dynamics (CFD) software

which conducted by fluid-solid coupling finite element. The temperature distribution and the heat exchange of IB

OB BSS under 200 MW

500 MW

1 GW and 1.5 GW conditions were analyzed.

Results

The temperature distribution of the BSS

the heat exchange of the internal fluid and the average temperature change of the fluid were obtained under four working conditions.

Conclusion

The maximum temperature of the IB BSS and the OB BSS is less than the allowable temperature of the structural material; the average temperature change of the coolant on the IB and OB channels is consistent with the blanket outlet and inlet.

关键词

Keywords

references

Song Y T , Wu S T , Li J G , et al . Concept design of CFETR tokamak machine [J ] . IEEE Transactions on Plasma Science , 2014 , 42 ( 3 ): 503 - 509 . DOI: 10.1109/TPS.2014.2299377 http://dx.doi.org/10.1109/TPS.2014.2299377 .

郭超 , 宋云涛 , 雷明准 , 等 . CFETR氦冷固态包层设计及热工水力学分析 [J ] . 核技术 , 2018 , 41 ( 4 ): 040601 . DOI: 10.11889/j.0253-3219.2018.hjs.41.040601 http://dx.doi.org/10.11889/j.0253-3219.2018.hjs.41.040601 .

GUO Chao , SONG Yuntao , LEI Mingzhun , et al . Design and thermal-hydraulic analysis of helium cooled solid breeder for CFETR [J ] . Nuclear Techniques , 2018 , 41 ( 4 ): 040601 . DOI: 10.11889/j.0253-3219.2018.hjs.41.040601 http://dx.doi.org/10.11889/j.0253-3219.2018.hjs.41.040601 .

Nie X C , Li J , Liu S L , et al . Global variance reduction method for global Monte Carlo particle transport simulations of CFETR [J ] . Nuclear Science and Techniques , 2017 , 28 ( 8 ): 115 . DOI: 10.1007/s41365-017-0270-3 http://dx.doi.org/10.1007/s41365-017-0270-3 .

Chen H , Li M , LYU Z , et al . Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR [J ] . Fusion Engineering and Design , 2015 , 96 : 89 - 94 . DOI: 10.1016/j.fusengdes.2015.02.045 http://dx.doi.org/10.1016/j.fusengdes.2015.02.045 .

Liu S , Li X , Ma X , et al . Updated design of water-cooled breeder blanket for CFETR [J ] . Fusion Engineering and Design , 2019 . DOI: 10.1016/j.fusengdes.2019.03.023 http://dx.doi.org/10.1016/j.fusengdes.2019.03.023 .

高芳芳 , 张小康 , 祝庆军 , 等 . CFETR水冷陶瓷包层中子学试验模块初步设计与分析 [J ] . 核聚变与等离子体物理 , 2017 , 37 ( 1 ): 87 - 93 . DOI: 10.16568/j.0254-6086.201701016 http://dx.doi.org/10.16568/j.0254-6086.201701016 .

GAO Fangfang , ZHANG Xiaokang , ZHU Qingjun , et al . Preliminary design and neutronics analysis of CFETR WCCB experimental mock-up [J ] . Fusion and Plasma Physics , 2017 , 37 ( 1 ): 87 - 93 . DOI: 10.16568/j.0254-6086.201701016 http://dx.doi.org/10.16568/j.0254-6086.201701016 .

魏川子 , 宋云涛 , 雷明准 . CFTER包层第一壁热工水力分析 [J ] . 核聚变与等离子体物理 , 2016 , 36 ( 1 ): 65 - 70 . DOI: 10.16568/j.0254-6086.201601012 http://dx.doi.org/10.16568/j.0254-6086.201601012 .

WEI Chuanzi , SONG Yuntao , LEI Mingzhun . CFETR thermal-hydraulic analysis of CFETR blanket first wall [J ] . Fusion and Plasma Physics , 2016 , 36 ( 1 ): 65 - 70 . DOI: 10.16568/j.0254-6086.201601012 http://dx.doi.org/10.16568/j.0254-6086.201601012 .

Martelli E , Giannetti F , Caruso G , et al . Study of EU DEMO WCLL breeding blanket and primary heat transfer system integration [J ] . Fusion Engineering and Design , 2018 , 136 : 828 - 833 . DOI: 10.1016/j.fusengdes.2018. 04.016 http://dx.doi.org/10.1016/j.fusengdes.2018. 04.016 .

Liu S , Ma X , Jiang K , et al . Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology [J ] . Fusion Engineering and Design , 2017 , 124 : 865 - 870 . DOI: 10.1016/j.fusengdes.2017.02.065 http://dx.doi.org/10.1016/j.fusengdes.2017.02.065 .

吕中良 . CFETR氦冷固态氚增殖剂包层中子学设计及性能研究 [D ] . 合肥 : 中国科学技术大学 , 2016 .

LYU Zhongliang . Neutronics design and analysis of helium cooled solid breeder blanket for CFETR [D ] . Hefei : University of Science and Technology of China , 2016 .

Cui Z X , Li X , Shu S B , et al . Calculation of the heat flux in the lower divertor target plate using an infrared camera diagnostic system on the experimental advanced superconducting tokamak [J ] . Nuclear Science and Techniques , 2019 , 30 ( 6 ): 94 . DOI: 10.1007/s41365-019-0625-z http://dx.doi.org/10.1007/s41365-019-0625-z .

Niu Q , Wang N X . Study of heat transfer by using DEM–CFD method in a randomly packed pebble-bed reactor [J ] . Nuclear Science and Techniques , 2019 , 30 ( 2 ): 28 . DOI: 10.1007/s41365-019-0556-8 http://dx.doi.org/10.1007/s41365-019-0556-8 .

Wan B , Ding S , Qian J , et al . Physics design of CFETR: determination of the device engineering parameters [J ] . IEEE Transactions on Plasma Science , 2014 , 42 ( 3 ): 495 - 502 . DOI: 10.1109/TPS.2013.2296939 http://dx.doi.org/10.1109/TPS.2013.2296939 .

Chan V S , Costley A E , Wan B N , et al . Evaluation of CFETR as a fusion nuclear science facility using multiple system codes [J ] . Nuclear Fusion , 2015 , 55 ( 2 ): 023017 .

陈磊 . 水冷包层增殖球床热机械性能研究 [D ] . 合肥 : 中国科学技术大学 , 2017 .

CHEN Lei . Thermo-mechanical study of pebble beds for water cooled ceramic breeder blanket [D ] . Hefei : University of Science and Technology of China , 2017 .

Martelli E . Thermal hydraulic design of DEMO water cooled lithium lead breeding blanket and integration with primary system and balance of plant [D ] . Roma : Sapienza University of Roma , 2018 .

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

暂无数据