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Yamano, Hidemasa; Xu, Y.*; Sago, Hiromi*; Hirota, Kazuo*; Baba, Takeo*
Proceedings of 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016) (CD-ROM), p.1029 - 1038, 2016/04
This study conducted the flow-induced vibration evaluation of the primary hot-leg piping in the demonstration reactor design of advanced loop-type sodium-cooled fast reactor in order to confirm the integrity of the piping. Following the description of the primary hot-leg piping design and a design guideline of the flow-induced vibration evaluation, this paper describes mainly the flow-induced vibration evaluation and thereby the integrity assessment. In the fatigue evaluation for the flow-induced vibration, the pipe stresses considering the stress concentration factor and so on, at representative locations were less than the design fatigue limit. Therefore, this evaluation confirmed the integrity of the primary hot-leg piping in the demonstration reactor.
Sakai, Takaaki; Yamano, Hidemasa; Tanaka, Masaaki; Ono, Ayako; Ohshima, Hiroyuki; Kaneko, Tetsuya*; Hirota, Kazuo*; Sago, Hiromi*; Xu, Y.*; Iwamoto, Yukiharu*; et al.
Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 13 Pages, 2013/05
The development of flow-induced vibration evaluation methodology has reached a milestone that separate-effect experimental data under a high Reynolds number regime including swirl and deflected inflow conditions are available for the validation of the methodology. On the other hand, technical standards are desirable to be documented for designers of sodium-cooled fast reactors. From such a background, the documentation of a flow-induced vibration design guideline has been made for the hot-leg piping of Japan sodium-cooled fast reactor. This paper describes the design guideline of the flow-induced vibration evaluation methodology, which has been informed from main separate-effect experiments, as well as supplemental interpretation for the guideline.
Yamano, Hidemasa; Sago, Hiromi*; Hirota, Kazuo*; Hayakawa, Satoshi*; Xu, Y.*; Tanaka, Masaaki; Sakai, Takaaki
Journal of Fluid Science and Technology (Internet), 7(3), p.329 - 344, 2012/09
As part of the development of a flow-induced vibration evaluation methodology for the primary cooling piping in Japan Sodium-cooled Fast Reactor, important factors were discussed in evaluating the flow-induced vibration for the hot-leg piping. To investigate a complex flow near the inlet of the hot-leg piping, a reactor scale numerical analysis was carried out for the reactor upper plenum flow, which was simulated in a 1/10-scale reactor upper plenum experiment. Based on this analysis, experimental conditions on swirl inflow and deflected inflow that were identified as important factors were determined for flow-induced vibration experiments simulating only the hot-leg piping. In this study, the effect of the swirl inflow on flow pattern and pressure fluctuation onto the pipe wall was investigated in a 1/3-scale hot-leg pipe experiment. The experiment has indicated less significant for the pressure fluctuations, while the flow separation region was slightly influenced by the swirl flow. Computational fluid dynamics simulation results also appear in this paper, focusing on its applicability to the hot-leg piping experiments.
Baba, Takeo*; Hirota, Kazuo*; Sago, Hiromi*; Yamano, Hidemasa; Aizawa, Kosuke; Xu, Y.*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 9 Pages, 2011/10
Yamano, Hidemasa; Sakai, Takaaki; Tanaka, Masaaki; Sago, Hiromi*; Hirota, Kazuo*; Xu, Y.*
Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 8 Pages, 2011/10
Hirota, Kazuo*; Ishitani, Yoshihide*; Nishida, Keigo*; Sago, Hiromi*; Xu, Y.*; Yamano, Hidemasa; Nakanishi, Shigeyuki; Kotake, Shoji
Proceedings of 6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-6) (USB Flash Drive), 8 Pages, 2008/11
CFD simulation using the Reynolds stress model was performed to evaluate turbulence-induced forces on the piping. The turbulence energy with the CFD simulation was compared with pressure fluctuation distributions obtained by the test with a 1/3 scale elbow simulating the JSFR hot-leg piping. The profile of turbulence energy was good agreement with that of the pressure fluctuation. The magnitude of pressure fluctuation can also be estimated from calculated turbulence energy multiplied by a certain coefficient. In the vibration analysis, the power spectrum density (PSD) of the pressure fluctuation was derived from the measured normalized PSD multiplied by the coefficient. The vibration analysis method was proposed based on the PSDs derived by the above procedure and correlation lengths. The analysis results of vibration response showed good agreement with the flow-induced-vibration test results, thereby it can be said that the vibration analysis method developed in this study is valid.
Hirota, Kazuo*; Ishitani, Yoshihide*; Nakamura, Tomomichi*; Shiraishi, Tadashi*; Sago, Hiromi*; Yamano, Hidemasa; Kotake, Shoji
Proceedings of 9th International Conference on Flow-induced Vibrations (FIV 2008), 6 Pages, 2008/00
The present study is intended to grasp flow-induced vibration characteristics in the piping by newly taken experimental data as well as to verify a vibration analysis tool with its data. It was found that a flow velocity-dependent periodic phenomenon with maximum random vibration force appears in the downstream region of the elbow. The Strouhal number of dominant pressure fluctuations in the downstream of elbow is estimated to be around 0.45. In addition, the validity of the analytical tool was confirmed by comparing between analysis and experiment.
Sago, Hiromi*; Hirota, Kazuo*; Ishitani, Yoshihide*; Yamano, Hidemasa; Kotake, Shoji
no journal, ,
A flow-induced vibration test has been performed with a 1/3 scale steel pipe simulating a actual FBR piping in order to establish a flow-induced-vibration evaluation method of a hot-leg piping in FBR. This test has measured a random vibration response and natural frequency of piping for the verification of the flow-induced-vibration evaluation method.
Hirota, Kazuo*; Ishitani, Yoshihide*; Uda, Nobuki*; Sago, Hiromi*; Yamano, Hidemasa; Kotake, Shoji
no journal, ,
A random vibration response has been calculated using correlation lengths and pressure-fluctuation power spectrum desities, which correspond to the input of a flow-induced-vibration analysis, obtained by a 1/3 scale water test simulating a FBR hot-leg piping.
Baba, Takeo*; Hirota, Kazuo*; Sago, Hiromi*; Yamano, Hidemasa; Aizawa, Kosuke; Xu, Y.*
no journal, ,
no abstracts in English
Yamano, Hidemasa; Sakai, Takaaki; Tanaka, Masaaki; Hirota, Kazuo*; Sago, Hiromi*; Xu, Y.*
no journal, ,
no abstracts in English
Yamano, Hidemasa; Sago, Hiromi*; Hirota, Kazuo*; Xu, Y.*; Tanaka, Masaaki; Kaneko, Tetsuya; Sakai, Takaaki
no journal, ,
no abstracts in English
Hirota, Kazuo*; Baba, Takeo*; Sago, Hiromi*; Xu, Y.*; Kaneko, Tetsuya; Yamano, Hidemasa
no journal, ,
no abstracts in English
Yamano, Hidemasa; Tanaka, Masaaki; Kaneko, Tetsuya; Sakai, Takaaki; Sago, Hiromi*; Hirota, Kazuo*; Xu, Y.*
no journal, ,
Experimental and analytical evaluation have been carried out to understand flow-induced-vibration characteristics of large-diameter elbow pipings and to develop its assessment methodology for ensuring the feasibility of sodium fast reactor design with two-loop cooling system for the increase of reactor power output. Proposed guideline of flow-induced vibration evaluation for hot-leg piping has been developed compling their research results.
Baba, Takeo*; Hirota, Kazuo*; Sago, Hiromi*; Xu, Y.*; Yamano, Hidemasa; Kaneko, Tetsuya
no journal, ,
no abstracts in English
Xu, Y.*; Sago, Hiromi*; Hirota, Kazuo*; Baba, Takeo*; Yamano, Hidemasa
no journal, ,
Structural integrity evaluation has been carried out for a hot-leg pipe due to random vibration induced by turbulence of pipe flow using "proposed guideline of flow-induced vibration evaluation for the primary hot-leg piping in sodium-cooled fast reactor", which has reflected the R&D results of the flow-induced vibration for a large-diameter piping. This gave the prospect of integrity of the primary hot-leg piping in the demonstration fast reactor.