Shirou Takahashi
Hitachi
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Featured researches published by Shirou Takahashi.
10th International Conference on Nuclear Engineering, Volume 1 | 2002
Shirou Takahashi; Hiroaki Tamako; Tsutomu Kawamura; Kouji Shiina; Masaaki Tsubaki; Akihiro Sakashita; Norimichi Yamashita; Tadashi Narabayashi; Tsuyoshi Hagiwara; Hideo Komita
For the purpose of shortening outage schedules, fixed type guide rods are expected to be used in the ABWR. Guide rods are the component for a shroud head and a steam dryer installation. However, guide rods are located near the main steam nozzle, therefore flow-induced vibration (FIV) is concern due to the high steam velocity. In the present study, tests of the 1/1.87-scale model and computational fluid dynamics (CFD) analysis for the 1/1.87-scale test and the actual ABWR model were conducted to prove the structural integrity of fixed type guide rods against FIV. As a result of CFD calculation, reduced damping was more than 5 and reduced velocity was approximately 1.44, so resonance did not occur fixed type guide rods. The maximum fluctuating stresses were conservatively evaluated as 8 MPa by the turbulence and 2 MPa by the Karman vortex shedding. Both values were below allowable limit. As noted above, the structural integrity against FIV was confirmed, so it is feasible to use the fixed type guide rods in the ABWR. (authors)
10th International Conference on Nuclear Engineering, Volume 2 | 2002
Shirou Takahashi; Kousei Umemori; Kooji Shiina; Tetsuya Totani; Akihiro Sakashita; Norimichi Yamashita; Takahisa Kondo
It is possible to simplify the reactor internal pump power supply system in the ABWR without affecting the core flow supply when a trip of all RIPs event occurs by eliminating the motor-generator sets and increasing the rotating inertia of the RIPs. This inertia increase due to an additional flywheel, which leads to a gain in weight and length, requires a larger diameter nozzle with a thicker sleeve. However, a thicker sleeve nozzle and a longer and heavier motor casing may change the RIP performance. In the present study, the inertia-increased RIP was verified through full-scale tests. The rotating inertia time constant for coastdown characteristics (behavior of the RIP speed in the event of power loss) for the inertia-increased RIP was doubled compared with the current RIP. The inertia-increased RIP with the thicker sleeve nozzle maintained good performance and its power supply system without motor-generator sets was judged appropriate for the ABWR.Copyright
Proceedings of the 8th International Symposium on Flow Modeling and Turbulence Measurements | 2002
Shirou Takahashi; Kouji Shiina
Archive | 2006
Masaya Ohtsuka; Kiyoshi Fujimoto; Shirou Takahashi; Fumihito Hirokawa; Masaaki Tsubaki
Heat Transfer Research | 2003
Koji Shiina; Shirou Takahashi; Yukihiro Asada
Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2007
Shirou Takahashi; Kenichi Nihei; Satoshi Kanno; Shoji Hayashi; Kouji Shiina; Minoru Ootaka
Transactions of the Japan Society of Mechanical Engineers. B | 2006
Shirou Takahashi; Hideo Soneda; Kenichi Yasuda; Kouji Shiina; Toshihiko Fukuda; Jun Mizutani; Norimichi Yamashita; Nobuhiko Ishiguro; Toru Matsuda
The Proceedings of the National Symposium on Power and Energy Systems | 2004
Shirou Takahashi; Hideo Soneda; Kenichi Yasuda; Kouji Shiina; Toshihiko Fukuda; Jun Mizutani; Masanobu Watanabe; Satoko Tajima
Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2003
Shirou Takahashi; Hideo Soneda; Kenichi Yasuda; Kouji Shiina; Seiichi Matsumura; Akihiro Sakashita; Norimichi Yamashita; Nobuhiko Ishiguro; Toru Matsuda
The Proceedings of the National Symposium on Power and Energy Systems | 2002
Shirou Takahashi; Masaaki Tanaka; Seiichi Matsumura; Kouji Shiina; Akihiro Sakashita; Sanemichi Yamashita; Takahisa Kondo
