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Title: TEM examination of phases formed between U–Pu–Zr fuel and Fe

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1252516
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 467 Journal Issue: P2; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English
Citation Metrics:
Cited by: 4 works
Citation information provided by
Web of Science

References (15)

Fe-Pu-U-Zr (Iron-Plutonium-Uranium-Zirconium) journal July 2003
Constituent redistribution in U–Pu–Zr fuel during irradiation journal April 2004
Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures journal September 1993
Crystal structure of high-Zr inclusions in an alloy containing U, Pu, Np, Am, Zr and rare-earth elements journal May 2014
Interdiffusion behavior in UPuZr fuel versus stainless steel couples journal December 1996
Analysis of constituent redistribution in the γ (bcc) U–Pu–Zr alloys under gradients of temperature and concentrations journal June 2000
Metallic fast reactor fuel fabrication for the global nuclear energy partnership journal July 2009
Casting of metallic fuel containing minor actinide additions journal September 1993
Reactions between U–Zr alloys and Fe at 923 K journal December 1997
Interdiffusion between U-Zr fuel and selected Fe-Ni-Cr alloys journal April 1993
Formation of face-centered-cubic zirconium by mechanical attrition journal November 2002
Phase relations in the quaternary Fe–Pu–U–Zr system journal July 2002
Solidus and liquidus temperatures in the uranium-plutonium-zirconium system journal June 1988
Reactions of U–Zr alloy with Fe and Fe–Cr alloy journal November 1999
Molecular dynamics investigation of the structural stability of body-centered cubic zirconium nanofilms journal August 2012

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