Thermal hydraulics of sodium-cooled fast reactors; Key issues and highlights

Ninokata, Hisashi*; Kamide, Hideki

Key issues in thermal hydraulics are discussed in connection to the current Japan's sodium-cooled fast reactor development efforts. Design study and related researches of the Japan Sodium-cooled Fast Reactor (JSFR) are focused. Several innovative technologies, e.g., fully natural circulation decay heat removal and recriticality free core, have been investigated in order to achieve higher level of reactor safety. Preliminary evaluations are on-going. Here, progress of design study is introduced.

Language	:	English
Journal	:	Proceedings of 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) (CD-ROM)
Volume	:
Number	:
Pages	:	20 Pages
Publication Year/Month	:	2011/09
Meeting title	:	14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14)
Held date	:	2011/09
Location (city)	:	Toronto
Location (country)	:	Canada
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. : BB20111645
JAEA Abstracts No. : 39001606
Paper Submission No. : 9902

[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.