Evaluation technology of core melt accidents in sodium-cooled fast reactors; Development of a coupled neutronic and thermal-hydraulic analysis code system

Ishida, Shinya ; Tagami, Hirotaka*; Tobita, Yoshiharu*; Kawada, Kenichi ; Morita, Koji*

no abstracts in English

Language	:	Japanese
Journal	:	Nihon Genshiryoku Gakkai-Shi ATOMO
Volume	:	68
Number	:	1
Pages	:	p.16 - 20
Publication Year/Month	:	2026/01
Meeting title	:
Held date	:
Location (city)	:
Location (country)	:
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.3327/jaesjb.68.1_16
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	no keyword
Research Facility	:
Press Release	:
JAEA R&D Navigator	:
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. : AA20250356
JAEA Abstracts No. : 54000607
Paper Submission No. : 31040

[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.