Toru Mitsutake
Toshiba
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Featured researches published by Toru Mitsutake.
Nuclear Engineering and Design | 1997
Yuichi Yamamoto; Akehiko Hoshide; Toru Mitsutake; Shinichi Morooka
In a boiling water nuclear reactor (BWR), liquid film dryout may occur on a fuel rod surface when the fuel assembly power exceeds the critical power. The spacers supporting fuel rods affect on the thermal-hydraulic performance of the fuel assembly. The spacer is designed to enhance critical power significantly. If spacer effects for two-phase flow could be estimated analytically, the cost and time for the development of the advanced BWR fuel would be certainly decreased. The final goal of this study is to be able to analytically predict the critical power of a new BWR fuel assembly without any thermal-hydraulic tests. Initially, we developed the finite element code to estimate spacer effects on the droplet deposition. Then, using the developed code, the spacer effects were estimated for various spacer geometries in a plane channel and one subchannel of BWR fuel bundle. The estimated results of the spacer effects showed a possibility to analytically predict the critical power of a BWR fuel assembly.
12th International Conference on Nuclear Engineering (ICONE12) - 2004 | 2004
Naohisa Tamura; Tatsuya Hazuku; Tomoji Takamasa; Kaichiro Mishima; Toru Mitsutake; Sinichi Morooka
This report presents an experimental result on quenching which affected by the Radiation Induced Surface Activation. Increasing of quenching velocity requires that the cooling liquid can contact the heated surface, or a high wettability of the surface when quenching initiates. From this point of view, an experimental study to investigate the relationship between surface wettability and quenching was performed by use of an oxide semiconductor-coated material after γ-ray irradiation. The results showed that highly surface wettability or highly hydrophilic condition of a simulated fuel rod made of SUS was achieved, and the quenching velocities were increased up to 15% after 300 kGy 60 Co γ-ray irradiation.Copyright
10th International Conference on Nuclear Engineering (ICONE 10) | 2002
Yoshiaki Tsukuda; Hiroshi Hayashi; Koujun Isaka; Hirohisa Kaneko; Toru Mitsutake; Miyuki Akiba; Nobuaki Abe; Shinichi Morooka; Yasuhiro Masuhara; Riichiro Suzuki; Yuji Nishino
Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8 x 8 and 9 x 9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, post boiling transition (post-BT) tests by the use of full-scale test assemblies simulating 9 x 9 fuel were carried out to evaluate BWR fuel integrity. Two kinds of post-BT tests, the steady-state post-BT test and transient post-BT test were performed, and the test results were applied to development of new heat transfer and re-wet correlations for the estimation of fuel rod surface temperature. (authors)
Journal of Nuclear Science and Technology | 1995
Akira Inoue; Tatsuo Kurosu; Toshimasa Aoki; Makoto Yagi; Toru Mitsutake; Shin ichi Morooka
Archive | 1988
Makoto Ueda; Toru Mitsutake; Koichi Sakurada; Koji Hiraiwa; Yasuhiro Hattori; Mamoru Nagano; Hironori Echigoya
Archive | 2007
Toru Mitsutake; Yasushi Yamamoto; 徹 光武; 泰 山本
Atomic Energy Society of Japan | 1996
Yasushi Yamamoto; Shin ichi Morooka; Toru Mitsutake; Seiichi Yokobori; Jiro Kimura
Jsme International Journal Series B-fluids and Thermal Engineering | 2004
Toru Mitsutake; Fumihisa Kano; Tetsuo Oosato; Akio Sayano; Miyuki Akiba; Shinichi Morooka
The Proceedings of The Computational Mechanics Conference | 2011
Masato Fukuta; Yasushi Yamamoto; Toru Mitsutake
Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2007
Toru Mitsutake; Yasushi Yamamoto