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	Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core
	Liu, Limin; Zhang, Dalin; Li, Linfeng; Yang, Yicheng; Wang, Chenglong; Qiu, Suizheng; Su, G. H.
刊名	Applied Thermal Engineering
	2018
卷号	145页码:48-57
关键词	Experimental investigation Fluoride-salt-cooled high-temperature reactors High-Prandtl-number fluid Pebble bed
ISSN号	1359-4311
URL标识	查看原文
内容类型	期刊论文
URI标识	http://www.corc.org.cn/handle/1471x/2831183
专题	西安交通大学
推荐引用方式 GB/T 7714	Liu, Limin,Zhang, Dalin,Li, Linfeng,et al. Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core[J]. Applied Thermal Engineering,2018,145:48-57.
APA	Liu, Limin.,Zhang, Dalin.,Li, Linfeng.,Yang, Yicheng.,Wang, Chenglong.,...&Su, G. H..(2018).Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core.Applied Thermal Engineering,145,48-57.
MLA	Liu, Limin,et al."Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core".Applied Thermal Engineering 145(2018):48-57.

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