First analyses of concrete-corium solids surrogate for the Fukushima Daiichi severe accidents

Brissonneau, L.*; Gousseau, J.*; Piluso, P.*; Bouyer, V.*; Kitagaki, Toru ; Ikeuchi, Hirotomo ; Yano, Kimihiko ; Washiya, Tadahiro

In case of severe accident in a nuclear reactor, the mixture obtained from fuel core and pins (mainly UO $_{2}$ and zirconium), called corium, can penetrate the steel vessel and interact with the concrete, as in the Fukushima Daiichi NPP (1F) severe accidents. A specific test has been realized with a concrete similar to the one of the Fukushima Daiichi NPP (1F) and an "oxide metal" corium. Ten samples were collected from representative places (corium core, crust, vertical and horizontal interfaces) and examined by SEM and XRD. The talk will present some of the main features of the solids formed after CCI.

Language	:	French
Journal	:
Volume	:
Number	:
Pages	:
Publication Year/Month	:
Meeting title	:	Materiaux 2018
Held date	:	2018/11
Location (city)	:	Strasbourg
Location (country)	:	France
Patent information	:
PDF	:
Paper URL	:
DOI for research data	:	Link to research data related to this paper/report.
Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
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. : BB20181379
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.