Proposition for the future development of the advanced fast reactor cycle (from our experience), 3; Proposition for the high-temperature gas-cooled reactor development

Iyoku, Tatsuo

Since I got employment in the Japan Atomic Energy Agency in 1979, I have consistently engaged in high-temperature gas-cooled reactor development and experienced from HTTR design to its in-service operation. Based on this experience, I will make recommendations for future high-temperature gas-cooled reactor development at the conference. Typical recommendations are as follows: In future HTGR research and developments, HTTR should be positioned as a COF (center of facility).

Language	:	Japanese
Journal	:
Volume	:
Number	:
Pages	:
Publication Year/Month	:
Meeting title	:	日本原子力学会2019年秋の大会
Held date	:	2019/09
Location (city)	:	富山
Location (country)	:	日本
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	高温ガス炉; HTTR; HTTRの設計・運転; 臨界試験; 出力上昇試験; 安全性実証試験; 国際共同研究
Research Facility	:	HTTR(高温工学試験研究炉)
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. : BB20191028
JAEA Abstracts No. :
Paper Submission No. :

[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.