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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.
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.
Onozuka, Masanori*; Takeda, Nobukazu; Nakahira, Masataka; Shimizu, Katsusuke*; Nakamura, Tomomichi*
Fusion Engineering and Design, 69(1-4), p.757 - 762, 2003/09
Times Cited Count：2 Percentile：19(Nuclear Science & Technology)The dynamic behavior of the ITER tokamak assembly has been investigated. Three experimental models have been considered to validate the numerical analysis methods for the dynamic events, mainly seismic events. A 1/8-scaled tokamak model, which is based on the 1998 ITER design, is under construction. Non-linear vibration characteristics, such as damping, can only be identified by a full-scale model. Therefore, a full-scale gravity support structure for the coil system has been designed and will be tested. In addition, for the sub-scaled tokamak model, the VV is assumed to be a rigid structure. This assumption is to be verified using a 1/20-scaled model. The above experimental models and their testing conditions have analytically and numerically evaluated. For example, both the static and dynamic spring constants obtained by static analysis and eigen-value analysis, respectively, were evaluated to be in good agreement.
