Preparation and characterization of the simulated burnup americium; Containing uranium-plutonium mixed oxide fuel

Tanaka, Kosuke ; Osaka, Masahiko ; Miwa, Shuhei ; Hirosawa, Takashi ; Kurosaki, Ken*; Muta, Hiroaki*; Uno, Masayoshi*; Yamanaka, Shinsuke*

In order to investigate the effect on fuel thermophysical properties when adding americium and selected fission products to uranium-plutonium mixed fuel, simulated low decontamination MOX fuel with high burn-ups to 250 GWd/t, has been prepared and subjected to characterization tests, elastic moduli measurements, melting temperature measurement.

Language	:	English
Journal	:	Journal of Nuclear Materials
Volume	:	420
Number	:	1-3
Pages	:	p.207 - 212
Publication Year/Month	:	2012/01
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Patent information	:
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Paper URL	:	https://doi.org/10.1016/j.jnucmat.2011.10.004
DOI for research data	:
Keywords	:	no keyword
Research Facility	:	AGF(照射燃料試験施設)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:	大阪大学

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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:43.52 Category:Materials Science, Multidisciplinary
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Registration No. : AA20110015
JAEA Abstracts No. : 40000134
Paper Submission No. : 10067

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