Thermal-Hydraulic Estimation in Tight-Lattice Rod Bundles for Development of the Innovative Water Reactor for Flexible Fuel Cycle-Reference-Cited by-同舟云学术

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Thermal-Hydraulic Estimation in Tight-Lattice Rod Bundles for Development of the Innovative Water Reactor for Flexible Fuel Cycle

Published:2008 Issue: Volume:3 Page:99-109
ISSN:1881-6088
Container-title:Progress in Multiphase Flow Research
language:
Short-container-title:Progress in Multiphase Flow Research

Author:

KURETA Masatoshi,YOSHIDA Hiroyuki,TAMAI Hidesada,OHNUKI Akira,AKIMOTO Hajime

Publisher

The Japanese Society for Multiphase Flow

Subject

General Medicine

Reference29 articles.

1. [4] Tamai, H., Kureta, M., Liu, W., Sato, T., Nakatsuka, T., Watanabe, H., Ohnuki, A. and Akimoto, H., Data Report of Tight-lattice Rod Bundle Thermal-hydraulic Tests (III) - Rod-bowing Effect Test using 37-rod Bundle Simulated Water-cooled Breeder Reactor -, JAEA-Data/Code, 2007-011 (2007).

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2. Experimental Study on Capacitance Void Fraction Meters for High Temperature and High Pressure Conditions(Fluids Engineering);Transactions of the Japan Society of Mechanical Engineers Series B;2010

3. 10.3811/jjmf.23.597;JAPANESE JOURNAL OF MULTIPHASE FLOW;2010

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