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Портал Begell Электронная Бибилиотека e-Книги Журналы Справочники и Сборники статей Коллекции
Heat Transfer Research
Импакт фактор: 1.199 5-летний Импакт фактор: 1.155 SJR: 0.267 SNIP: 0.503 CiteScore™: 1.4

ISSN Печать: 1064-2285
ISSN Онлайн: 2162-6561

Выпуски:
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Heat Transfer Research

DOI: 10.1615/HeatTransRes.v30.i4-6.220
pages 411-421

Upward Two-Phase Flow in a Vertical Annular Channel (Effect of Spacer Geometry)

T. Fukano
Dept. of Environmental Symbiosis Engineering, Kurume Institute of Technology, Fukuoka, Japan
Ryu Egashira
Division of Mechanical Science, Graduate School of Engineering, Hokkaido University, Sapporo 060-8628, Japan
K. Naitoh
Department of Mechanical Engineering, Faculty of Engineering, Kyushu University, Fukuoka, Japan

Краткое описание

One concern in the thermal design of a safe and economic nuclear reactor, especially in a boiling water reactor (BWR), is the heat removal from the nuclear fuel rods near the rods supporting the spacers. The spacer must be carefully designed focusing attention on the geometry of the spacer. The purpose of the present paper is to experimentally investigate the effect of the spacer geometry on the film breakdown near the spacer. A ring and a grid type spacers were used in the present experiment. Judging from the frequency of the dry patch formation and the temperature distribution near the spacer it is demonstrated that the ring type spacer is better than the grid type spacer.


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