Austenite-based stainless steel irradiation behavior of the precipitate and void swelling

Inoue, Toshihiko ; Sekio, Yoshihiro ; Watanabe, Hideo*

For the evaluation of irradiated segregation behavior, Austenite-based stainless steel for the fast reactor, during irradiation was evaluated by utilizing TIARA facility (Irradiate temperature: 600 $^{circ}$ C, Dose: 100 dpa) was observed by analytical electron microscope (JEM-ARM20FC). As a result of observation, the large-size void is observed in irradiation area, and MX segregation (containing Niobium) is not observed. In un-irradiation area the MX segregation is observed. And it is observed conspicuously that Nickel is segregation on the void surface. By the latest high-performance TEM utilization, these phenomenon are able to visualize. It is expected for the clarification of the irradiation damage and mechanism of void swelling, by the analyzing these phenomenon utilization with the latest high-performance TEM utilization.

Language	:	Japanese
Journal	:	Materia
Volume	:	58
Number	:	2
Pages	:	P. 92
Publication Year/Month	:	2019/02
Meeting title	:
Held date	:
Location (city)	:
Location (country)	:
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.2320/materia.58.92
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	高速炉炉心材料; 照射誘起偏析; ボイドスウェリング
Research Facility	:	MMF(照射材料試験施設)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	九州大学

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. : AA20180152
JAEA Abstracts No. : 47000671
Paper Submission No. : 21303

[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.