In situ tritium recovery from Li $_{2}$ O irradiated in a fast neutron flux; BEATRIX-II, Phase II temperature-change canister

Slagle, O. D.*; Kurasawa, Toshimasa; Takahashi, Tadashi; Hollenberg, G. W.*; Verrall, R. A.*

no abstracts in English

Language	:	English
Journal	:	Journal of Nuclear Materials
Volume	:	219
Number	:
Pages	:	p.265 - 273
Publication Year/Month	:	1995/03
Meeting title	:	Fabrication and Properties of Ceramics for Fusion Energy
Held date	:	1994/04
Location (city)	:	Indianapolis
Location (country)	:	U.S.A.
Patent information	:
PDF	:
Paper URL	:	https://doi.org/10.1016/0022-3115(94)00401-3
DOI for research data	:
Keywords	:	酸化リチウム; トリチウム回収; 照射量依存性; 高速中性子照射
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™	:	Percentile:43.23 Category:Materials Science, Multidisciplinary
Altmetrics	:

Registration No. : B19930562
JAEA Abstracts No. :
Paper Submission No. : 6925

[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.

In situ tritium recovery from LiO irradiated in a fast neutron flux; BEATRIX-II, Phase II temperature-change canister

In situ tritium recovery from Li $_{2}$ O irradiated in a fast neutron flux; BEATRIX-II, Phase II temperature-change canister