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Journal Articles

Fast reactor core seismic experiment and analysis under strong excitation

Yamamoto, Tomohiko; Iwasaki, Akihisa*; Kawamura, Kazuki*; Matsubara, Shinichiro*; Harada, Hidenori*

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 8 Pages, 2018/07

To design fast reactor (FR) core components, seismic response must be evaluated in order to ensure structural integrity. Thus, a core seismic analysis method has been developed to evaluate 3D core vibration behavior considering fluid structure interaction and vertical displacements (rising). 1/1.5 scale 37 core element mock-ups hexagonal-matrix experiment was performed to validate the core elements vibration analysis code in three dimensions (REVIAN-3D). Based on the test data, the analysis model newly incorporated to respond to strong excitation was verified.

Journal Articles

Roll wave effects on annular condensing heat transfer in horizontal PCCS condenser tube

Kondo, Masaya; Nakamura, Hideo; Anoda, Yoshinari; Saishu, Sadanori*; Obata, Hiroyuki*; Shimada, Rumi*; Kawamura, Shinichi*

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 9 Pages, 2002/00

no abstracts in English

Journal Articles

Analysis of multi-dimensional boiling flow in secondary water pool of horizontal PCCS; Effect of pool size

Onuki, Akira; Nakamura, Hideo; Kawamura, Shinichi*; Saishu, Sadanori*

Nihon Kikai Gakkai Netsu Kogaku Koenkai Koen Rombunshu, p.31 - 32, 2001/11

A passive containment cooling system (PCCS) is under planning to use in a next-generation-type BWR for long-term cooling by condensing steam using horizontal heat exchangers. Heat transfer behavior in a secondary water pool is one of important phenomena governing heat removal performance of the PCCS. Boiling and condensation can be supposed under high heat flux regions and the characteristics of the two-phase natural circulation should be evaluated. This study investigated effects of pool size on the characteristics by multi-dimensional two-fluid model code ACE-3D. It was found from the analyses that the pool size gives no significant influences for the characteristics in tube bundle under local-boiling mode.

Journal Articles

Comparison of calculated alues with measured values on the amount of TRU and FP nuclides accumulated in gadolinium bearing PWR spent fuels

Adachi, Takeo; Nakahara, Yoshinori; Kono, Nobuaki; Gunji, Katsubumi; ; ; ; Kato, Kaneharu; Tachikawa, Enzo; *; et al.

Journal of Nuclear Science and Technology, 31(10), p.1119 - 1129, 1994/10

 Times Cited Count:8 Percentile:60.26(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Development of seismic assessment method for FR core, 2; Seismic experiment of full scale single model of control rod

Yamamoto, Tomohiko; Iwasaki, Akihisa*; Kawamura, Kazuki*; Matsubara, Shinichiro*; Ikarimoto, Iwao*; Harada, Hidenori*

no journal, , 

A sophisticated analysis method has to be developed to study the seismic response of Fast Reactor (FR) core considering 3 dimensional group vibration of FR core components. This paper summarizes for result of vertical vibration experiment of full scale single model of control rod.

Oral presentation

Development of seismic assessment method for FR core, 3; Summary of development of FR core seismic analysis method

Yamamoto, Tomohiko; Matsubara, Shinichiro*; Iwasaki, Akihisa*; Kawamura, Kazuki*; Harada, Hidenori*

no journal, , 

A fast reactor core consists of hundreds of core elements, which lengthen due to thermal expansion and swelling. So, the core elements are self-standing on the core support structure and not restrained in the axial direction. The authors carried out vibration tests and verification of analysis code (REVIAN-3) to evaluate 3D core vibration behavior. This report describes the summary of some experimental results and analysis.

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