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Featured researches published by Shirou Takahashi.


10th International Conference on Nuclear Engineering, Volume 1 | 2002

Evaluation of Flow-Induced Vibration for Fixed Type Guide Rods of Shroud Head and Steam Dryer in ABWR

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

Development of an Inertia-Increased ABWR Internal Pump

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

TURBULENCE MIXING AND TEMPERATURE FLUCTUATION OF HOT AND COLD FLUIDS IN TEE PIPES

Shirou Takahashi; Kouji Shiina


Archive | 2006

Study on acoustic resonance and its damping of BWR steam dome

Masaya Ohtsuka; Kiyoshi Fujimoto; Shirou Takahashi; Fumihito Hirokawa; Masaaki Tsubaki


Heat Transfer Research | 2003

Flashing characteristics in a pipe downstream from a depressurizing tank and temperature fluctuation characteristics at a mixing tee junction with cold water injection

Koji Shiina; Shirou Takahashi; Yukihiro Asada


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2007

ICONE15-10244 DEVELOPMENT OF COOLING TECHNIQUES FOR INDUCTION HEATING STRESS IMPROVEMENT OF REACTOR RECIRCULATION INLET NOZZLE

Shirou Takahashi; Kenichi Nihei; Satoshi Kanno; Shoji Hayashi; Kouji Shiina; Minoru Ootaka


Transactions of the Japan Society of Mechanical Engineers. B | 2006

Analytical Evaluation of Flow and Flow Induced Vibration Characteristics in the ABWR Lower Plenum

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

Evaluation of the Flow Characteristics in the Lower Plenum of the ABWR

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

ICONE11-36393 EVALUATION OF FLOW CHARACTERISTICS IN THE LOWER PLENUM OF THE ABWR BY USING CFD ANALYSIS

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

Development of ABWR Internal Pump with Thicker Sleeve Nozzle

Shirou Takahashi; Masaaki Tanaka; Seiichi Matsumura; Kouji Shiina; Akihiro Sakashita; Sanemichi Yamashita; Takahisa Kondo

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Norimichi Yamashita

Tokyo Electric Power Company

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Akihiro Sakashita

Tokyo Electric Power Company

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