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Kureta, Masatoshi; Tamai, Hidesada
Proceedings of 5th International Conference on Multiphase Flow (ICMF 2004) (CD-ROM), 10 Pages, 2004/06
3D void fraction distribution of boiling flow in a tight-lattice 7-rod bundle was measured by neutron radiography 3D computed tomography (neutron tomography) to investigate the flow characteristics in tight-lattice rod bundles and to verify the numerical analysis codes. The test section simulates the fuel rod bundle of the RMWR and consists of 7 heater rods with gap of 1.0mm and with diameter of 12.0mm. In this paper, the neutron tomography system, experiments and comparison of the measured data with a subchannel analysis code, COBRA-TF, are reported. It was found from this experiment that water layer which surrounds the heater rod becomes thick between rods, narrow region, and steam accumulates at the center region among three rods. COBRA-TF code overestimates the void fraction in a tight-lattice bundle compared with the present data.
Hayashi, Mitsuhiko*; Takai, Shigeomi*; Sakaguchi, Hiroki*; Matsubayashi, Masahito; Esaka, Takao*
Kashika Joho Gakkai-Shi, 20(suppl.1), p.375 - 376, 2000/07
no abstracts in English
Nakayama, Jiro; Sumi, Hirotaka; Kuboki, Michikatsu; Kodaka, Akira; Fujiwara, Koji
no journal, ,
no abstracts in English
Sato, Yuki
no journal, ,
no abstracts in English
Sato, Yuki
no journal, ,
no abstracts in English