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18th International Conference on Nuclear Engineering: Volume 5 | 2010

Fluctuating Pressure Generating in BWR Main Steam Lines Acoustic Excited by Safety Relief Valve Stub Pipes and Dead Legs

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

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)


Archive | 2005

BOILING WATER REACTOR AND ITS ACOUSTIC VIBRATION SUPPRESSION METHOD

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

Natural circulation boiling water reactor and handling method thereof

Atsushi Watanabe; Yoichi Wada; Makoto Nagase; Kazushige Ishida; Hideyuki Hosokawa; Fumihito Hirokawa; Masaaki Tsubaki; Shiro Takahashi


Archive | 2011

Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor

Masaya Ohtsuka; Kiyoshi Fujimoto; Masaaki Tsubaki


Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance | 2009

Flow Visualization of Acoustic Resonance for Safety Relief Valves in Power Uprated BWRs

Keita Okuyama; Shiro Takahashi; Akinori Tamura; Koji Nishida; Masaya Ohtsuka; Masaaki Tsubaki


Nuclear Engineering and Design | 2012

Flow-induced acoustic resonance at the mouth of one or two side branches

Keita Okuyama; Akinori Tamura; Shiro Takahashi; Masaya Ohtsuka; Masaaki Tsubaki


Archive | 2006

Study on acoustic resonance and its damping of BWR steam dome

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


The Proceedings of the International Conference on Nuclear Engineering (ICONE) | 2015

ICONE23-1827 DEVELOPMENT OF REACTOR INTERNALS IN RBWR (RESOURCE-RENEWABLE BWR) FOR RECYCLING AND TRANSMUTATION OF TRANSURANIUM ELEMENTS

Shiro Takahashi; Yuichi Koide; Kiyoshi Fujimoto; Hideki Hosoi; Sadakatsu Sawahata; Hidenori Tanaka; Takehiro Seto; Masaaki Tsubaki; Tetsushi Hino; Masaya Ohtsuka


Archive | 2010

EVALUATING METHOD FOR INTEGRITY OF VIBRATION OF STEAM DRYER AND TEST DEVICE STEAM DRYER

Shiro Takahashi; Masaya Ohtsuka; Koji Nishida; Takashi Ito; Yasuhiro Mabuchi; Akinori Tamura; Masaaki Tsubaki; Keita Okuyama; Kazuhiro Yoshikawa

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