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超临界水冷堆类三角形子通道流动传热特性研究

王为术 张斌 雷佳 朱晓静 陈刚

原子能科学技术2016,Vol.50Issue(7):1193-1199,7.
原子能科学技术2016,Vol.50Issue(7):1193-1199,7.DOI:10.7538/yzk.2016.50.07.1193

超临界水冷堆类三角形子通道流动传热特性研究

Investigation on Flow and Heat Transfer Characteristics of Supercritical Water in Sub-channel with Triangular Distribution of SCWR

王为术 1张斌 1雷佳 1朱晓静 2陈刚1

作者信息

  • 1. 华北水利水电大学 热能工程研究中心,河南 郑州 450045
  • 2. 大连理工大学 能源与动力学院,辽宁 大连 116024
  • 折叠

摘要

Abstract

The physical model of the sub-channel within a triangular rod bundle,of which the rod diameter is 8 mm and the pitch-to-diameter ratio is 1.4,was built to numerically investigate the flow and heat transfer characteristics of supercritical water in the sub-channels of supercritical water-cooled reactor.The numerical investigation was performed within the range of pressure from 23 to 28 MPa,mass fluxes from 700 to 1 300 kg/(m2 ·s),and heat fluxes from 200 to 1 000 kW/m2 .By using the Reynolds stress turbulence model SSG,the effects of mass flux,pressure and heat flux on the flow and heat transfer characteristics were analyzed in detail,as well as the secondary flow characteristics in different enthalpy regions.The results show that the numerical results agree well with experimental results.The higher the mass flux is,the better the heat transfer performs.In the pseudo-critical enthalpy region,the peak of heat transfer coefficient decreases greatly with the increase of pressure and heat flux.The high heat flux induces high inner wall temperature and might cause the heat transfer deterioration. The obvious secondary flow is found in the direction perpendicular to the main flow,and six symmetrical vortices are formed in the cross section of sub-channel.The velocity of the secondary flow reaches a peak near the narrow gap.Although the structures of the secondary flow are similar in different enthalpy regions,the secondary flow velocity increases with bulk enthalpy.

关键词

超临界水冷堆/类三角形子通道/传热特性/二次流/数值模拟

Key words

supercritical water-cooled reactor/sub-channel with triangular distribution/heat transfer characteristic/secondary flow/numerical simulation

分类

能源科技

引用本文复制引用

王为术,张斌,雷佳,朱晓静,陈刚..超临界水冷堆类三角形子通道流动传热特性研究[J].原子能科学技术,2016,50(7):1193-1199,7.

基金项目

国家自然科学基金资助项目(51406026) (51406026)

河南省高校创新人才计划资助项目(2012 HASTIT018) (2012 HASTIT018)

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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