Masaaki Tsubaki
Hitachi
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18th International Conference on Nuclear Engineering: Volume 5 | 2010
Shiro Takahashi; Keita Okuyama; Akinori Tamura; Masaya Ohtsuka; Masaaki Tsubaki; Mabuchi Yasuhiro; Teppei Kubota; Yukio Ogawa; Fumio Inada; Ryo Morita
During operation, the BWR-3 steam dryer in the Quad Cities Unit 2 Nuclear Power Plant was damaged by high cycle fatigue. The dryer failure was attributed to flow-induced acoustic resonance at the stub pipes of safety relief valves (SRVs) in the main steam lines (MSLs). The acoustic resonance was considered to be generated by interaction between the sound field and an unstable shear layer across the closed side branches with SRV stub pipes. We HITACHI and CRIEPI have started a research program on BWR dryers to develop their loading evaluation methods. Moreover, it has become necessary to evaluate the dryer integrity of BWR-5 plants in particular which are the main type of BWR in Japan. In the present study, we used 1/10-scale BWR tests and analyses to investigate the flow-induced acoustic resonance and characteristics of fluctuating pressure in MSLs. The test apparatus consisted of a steam dryer, a steam dome and 4 MSLs with 20 SRV stub pipes. A finite element method (FEM) was applied for the calculation of three-dimensional wave equations in acoustic analysis. We demonstrated that remarkable fluctuating pressures occurred in high and low frequency regions. Intensity of three peaks observed in the spectrum of fluctuating pressure in MSLs was increased with St. High frequency fluctuating pressures were generated by the flow-induced acoustic resonance in the SRV stub pipes. Low frequency fluctuating pressures were excited by the acoustic resonance in the dead leg. Frequency of fluctuating pressure generating in the SRV stub pipe was changed with St. On the other hand, frequency of fluctuating pressure excited by dead leg was almost constant. Fluctuating pressure in low frequency range increased gradually with flow velocity and its intensity was roughly proportional to the square of flow velocity. The flow-induced acoustic resonance did not occur for St larger than 0.6 in the BWR MSLs for both low and high frequency ranges. Operating conditions of the BWR-5 from 100 to 115% were in the range of St larger than 0.6, so intense acoustic resonance would not occur in the BWR MSLs.Copyright
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)
Archive | 2005
Tadao Aoyama; Masao Chagi; Kiyoshi Fujimoto; Kazuaki Kito; Masaya Otsuka; Koji Shiina; Shiro Takahashi; Masaaki Tsubaki; 雅哉 大塚; 和明 木藤; 孝次 椎名; 椿 正昭; 雅夫 茶木; 清志 藤本; 肇男 青山; 志郎 高橋
Archive | 2007
Atsushi Watanabe; Yoichi Wada; Makoto Nagase; Kazushige Ishida; Hideyuki Hosokawa; Fumihito Hirokawa; Masaaki Tsubaki; Shiro Takahashi
Archive | 2011
Masaya Ohtsuka; Kiyoshi Fujimoto; Masaaki Tsubaki
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance | 2009
Keita Okuyama; Shiro Takahashi; Akinori Tamura; Koji Nishida; Masaya Ohtsuka; Masaaki Tsubaki
Nuclear Engineering and Design | 2012
Keita Okuyama; Akinori Tamura; Shiro Takahashi; Masaya Ohtsuka; Masaaki Tsubaki
Archive | 2006
Masaya Ohtsuka; Kiyoshi Fujimoto; Shirou Takahashi; Fumihito Hirokawa; Masaaki Tsubaki
The Proceedings of the International Conference on Nuclear Engineering (ICONE) | 2015
Shiro Takahashi; Yuichi Koide; Kiyoshi Fujimoto; Hideki Hosoi; Sadakatsu Sawahata; Hidenori Tanaka; Takehiro Seto; Masaaki Tsubaki; Tetsushi Hino; Masaya Ohtsuka
Archive | 2010
Shiro Takahashi; Masaya Ohtsuka; Koji Nishida; Takashi Ito; Yasuhiro Mabuchi; Akinori Tamura; Masaaki Tsubaki; Keita Okuyama; Kazuhiro Yoshikawa