Development of security and safety fuel for Pu-burner HTGR, 3; Fuel design and nuclear thermal design

Goto, Minoru ; Ueta, Shohei ; Aihara, Jun ; Fukaya, Yuji ; Inaba, Yoshitomo ; Tachibana, Yukio ; Kunitomi, Kazuhiko ; Okamoto, Koji*

In this study, a feasibility of the coated fuel particle for a plutonium burner High Temperature Gas-cooled Reactor (HTGR) is evaluated by calculating the inner pressure. Additionally, a feasibility of the reactor core is also evaluated by calculating the nuclear characteristics and the fuel temperature. This study is started in 2014 and will be completed in 2017. In 2014, the calculation codes and the input files for the evaluations were prepared.

Language	:	Japanese
Journal	:
Volume	:
Number	:
Pages	:
Publication Year/Month	:
Meeting title	:	日本原子力学会2015年秋の大会
Held date	:	2015/09
Location (city)	:	静岡
Location (country)	:	日本
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:
Keywords	:	高燃焼度; 燃料設計; 炉心核熱設計; プルトニウム; 高温ガス炉
Research Facility	:	HTTR(高温工学試験研究炉)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	東京大学

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. : BB20151629
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.