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Journal Articles

Investigation of water-vapor two-phase flow characteristics in a tight-lattice core by large-scale numerical simulation, 2; Experimental analysis of 2-channel fluid mixing tests

Nagayoshi, Takuji*; Yoshida, Hiroyuki; Onuki, Akira; Akimoto, Hajime

Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(1), p.16 - 24, 2005/03

A detailed gas-liquid two-phase flow analysis code based on an advanced interface-tracking method has been developed. It is expected that the developed code would be able to simulate two-phase cross flow behavior within tight-lattice fuel bundles without relying on any empirical correlations. In order to verify the applicability of the code to simulate two-phase cross flow behavior in such situations, numerical analyses of 2-channel model tests were conducted to compare the air slug deformation and separation behavior caused by cross flow through a narrow interconnection between channels. Although the code underestimated the ascending velocity of the slug, the calculated slug deformation and separation behavior were shown to be quite similar to those observed by a high-speed video camera. Moreover the minimum differential pressure between the subchannels through the interconnection, causing channel-to-channel air transfer to occur could be predicted to within 20Pa. However, further studies of modeling and implementation related to the interface-channel wall interaction, such as a contact angle of a gas-liquid interface at the channel wall, are required for prediction improvements. Nevertheless, the qualitative capability of the developed code to simulate two-phase cross flow phenomena was demonstrated.

Journal Articles

Evaluation of scale effects in tight-lattice bundles using subchannel analysis

Tamai, Hidesada; Yoshida, Hiroyuki; Masuko, Kenji*; Akimoto, Hajime

Proceedings of 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), p.230 - 236, 2004/12

no abstracts in English

JAEA Reports

Feasibility study on thermal-hydraulic design of reduced-moderation PWR-type core

Yoshida, Hiroyuki; Onuki, Akira; Akimoto, Hajime

JAERI-Tech 2000-024, p.31 - 0, 2000/03

JAERI-Tech-2000-024.pdf:2.06MB

no abstracts in English

Journal Articles

Measurements of the modified conversion ratio by gamma-ray spectrometry of fuel rods for water-moderated UO$$_{2}$$ cores

Nakajima, Ken; ; Suzaki, Takenori

Nuclear Science and Engineering, 116, p.138 - 146, 1994/00

 Times Cited Count:16 Percentile:78.48(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effect of fission gas release on burnup characteristics and void reactivity in HCLWRs

;

Journal of Nuclear Science and Technology, 24(8), p.668 - 670, 1987/08

 Times Cited Count:0 Percentile:0.43(Nuclear Science & Technology)

no abstracts in English

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