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

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.

Language	:	English
Journal	:	Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive)
Volume	:
Number	:
Pages	:	9 Pages
Publication Year/Month	:	2012/12
Meeting title	:	8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8)
Held date	:	2012/12
Location (city)	:	Beppu
Location (country)	:	Japan
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:
Keywords	:	no keyword
Research Facility	:
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:

Accesses	:	- Accesses
Web of Science® Times Cited Count	:	Times Cited Count： If you would like to get the latest times cited, please access the Web of Science®. http://www.webofknowledge.com/wos
InCites™	:
Altmetrics	:

Registration No. : BB20122184
JAEA Abstracts No. : 41000229
Paper Submission No. : 11849

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.