Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Flow-induced vibration evaluation of primary hot-leg piping in advanced loop-type sodium-cooled fast reactor for demonstration

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.

Journal Articles

Development of proposed guideline of flow-induced vibration evaluation for hot-leg piping in a sodium-cooled fast 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.

Journal Articles

Effect of swirl inflow on flow pattern and pressure fluctuation onto a single-elbow pipe in Japan Sodium-cooled Fast Reactor

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.

Journal Articles

Study on flow induced vibration evaluation for a large scale JSFR piping, 2; Vibration analysis in 1/3 scale hot-leg piping experiments under swirl inflow conditions

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, 2011/05

Journal Articles

Study on flow induced vibration evaluation for a large scale JSFR piping, 1; Current status of flow induced vibration evaluation for hot-leg piping

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, 2011/05

Journal Articles

Study on flow-induced-vibration evaluation of the large-diameter pipings in a sodium-cooled fast reactor, 3; Random vibration analysis method based on turbulence energy calculated by CFD

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.

Journal Articles

Flow-induced vibration of a large-diameter elbow piping in high Reynolds number range; Random force measurement and vibration analysis

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.

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 3; Vibration characteristics and random vibration response of 1/3 scaled model of hot leg piping

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.

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 4; Analysis method for random vibration of hot leg piping and its verification

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.

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 27; 1/3 scale hot-leg piping experiments and vibration analysis under swirl inflow conditions

Baba, Takeo*; Hirota, Kazuo*; Sago, Hiromi*; Yamano, Hidemasa; Aizawa, Kosuke; Xu, Y.*

no journal, , 

no abstracts in English

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 26; Progress in JFY2010

Yamano, Hidemasa; Sakai, Takaaki; Tanaka, Masaaki; Hirota, Kazuo*; Sago, Hiromi*; Xu, Y.*

no journal, , 

no abstracts in English

Oral presentation

Evaluation for flow-induced vibration of a primary circuit hot-leg piping in a sodium-cooled fast reactor, 1; Approach to the evaluation methodology development

Yamano, Hidemasa; Sago, Hiromi*; Hirota, Kazuo*; Xu, Y.*; Tanaka, Masaaki; Kaneko, Tetsuya; Sakai, Takaaki

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium-cooled fast reactor, 35; Development of proposed guideline of flow-induced vibration evaluation for hot-leg piping

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.

Oral presentation

Study on flow-induced vibration of large-diameter pipings in a sodium-cooled fast reactor, 36; 1/3 scale hot-leg piping experiments and vibration analysis under deflected inflow conditions

Baba, Takeo*; Hirota, Kazuo*; Sago, Hiromi*; Xu, Y.*; Yamano, Hidemasa; Kaneko, Tetsuya

no journal, , 

no abstracts in English

Oral presentation

Study on flow-induced-vibration evaluation of large-diameter pipings in a sodium cooled fast reactor, 45; Structural integrity evaluation of the primary hot leg pipe due to flow-induced vibration

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.

16 (Records 1-16 displayed on this page)
  • 1