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Journal Articles

Experimental study for the proposal of design measures against cover gas entrainment and vortex cavitation with 1/11th scale reactor upper sodium plenum model of Japan Sodium-cooled Fast Reactor

Yoshida, Kazuhiro*; Sakata, Hideyuki*; Sago, Hiromi*; Shiraishi, Tadashi*; Oyama, Kazuhiro*; Hagiwara, Hiroyuki*; Yamano, Hidemasa; Yamamoto, Tomohiko

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 9 Pages, 2012/12

To prevent the vortex cavitations, asymmetric flow in the upper plenum due to the radial slit with upper internal structure (UIS) has been mitigated by installing a cylindrical structure named as dummy plug instead of the fuel handling machine only used for refueling period. In this study, the extended brim and the division plate at the slit of UIS have been proposed in order to improve flow pattern in upper plenum for the purpose of the vortex cavitation prevention.

Journal Articles

Experimental demonstration on flow diodes applicable to a passive decay heat removal system for sodium-cooled reactors

Chikazawa, Yoshitaka; Aizawa, Kosuke; Shiraishi, Tadashi*; Sakata, Hideyuki*

Journal of Nuclear Science and Technology, 46(4), p.321 - 330, 2009/04

https://doi.org/10.3327/jnst.46.321
 Times Cited Count：6 Percentile：40.23(Nuclear Science & Technology)

Oral presentation

Performance test of decay heat removal system flow diode in sodium cooled reactor

Aizawa, Kosuke; Chikazawa, Yoshitaka; Shiraishi, Tadashi*; Sakata, Hideyuki*; Okubo, Yoshiyuki*

no journal, , 

no abstracts in English

Oral presentation

Experimental study for the proposal of design measures against cover gas entrainment and vortex cavitation with 1/11 scale reactor upper sodium plenum model of Japan Sodium-cooled Fast Reactor

Yoshida, Kazuhiro*; Sakata, Hideyuki*; Sago, Hiromi*; Shiraishi, Tadashi*; Oyama, Kazuhiro*; Hagiwara, Hiroyuki*; Yamano, Hidemasa; Yamamoto, Tomohiko

no journal, , 

no abstracts in English

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