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含绕丝2×2棒束内超临界水传热试验研究

王汉 毕勤成 吕海财

原子能科学技术2016,Vol.50Issue(8):1387-1394,8.
原子能科学技术2016,Vol.50Issue(8):1387-1394,8.DOI:10.7538/yzk.2016.50.08.1387

含绕丝2×2棒束内超临界水传热试验研究

Experimental Investigation on Heat Transfer of Supercritical Water in Wire-wrapped 2×2 Rod Bundle

王汉 1毕勤成 2吕海财2

作者信息

  • 1. 华北电力大学 核科学与工程学院,北京 102206
  • 2. 西安交通大学 动力工程多相流国家重点实验室,陕西 西安 710049
  • 折叠

摘要

Abstract

The experiment was performed to study the heat transfer of supercritical water in wire-wrapped 2 × 2 rod bundle under the background of supercritical water-cooled reactor fuel qualification test.The experimental parameters cover the pressure of 23 to 28 MPa,mass flux of 400 to 1 000 kg/(m2 ·s)and heat flux of 200 to 1 000 kW/m2 .The circumferential wall temperature distributions of the heated tubes were obtained.In addition,the effects of heat flux,mass flux,pressure and wire-wrapped spacer on wall temperature and heat transfer coefficient were analyzed.It is found that the wall temperatures along the circumferential direction of the heated tube are non-uniform and non-symmetric.The highest wall temperature appears either at the corner sub-channel,or at the location covered by the wrapped wire.The heat transfer coeffi-cient drops considerably with increasing heat flux or decreasing mass flux in the pseudo-critical region,but varies slightly at different pressures.Compared with the bare 2 ×2 rod bundle,the wire-wrapped spacer not only changes the circumferential wall tempera-ture profiles of the heat tube,but also promotes the average heat transfer coefficient.

关键词

超临界水/2×2 棒束/周向壁温/传热

Key words

supercritical water/2 × 2 rod bundle/circumferential wall temperature/heat transfer

分类

能源科技

引用本文复制引用

王汉,毕勤成,吕海财..含绕丝2×2棒束内超临界水传热试验研究[J].原子能科学技术,2016,50(8):1387-1394,8.

基金项目

中央高校基本科研业务费专项资金资助项目(2016ZZD05) (2016ZZD05)

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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