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Title: Behavior of metallic fast reactor fuels during an overpower transient

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1822573
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 557 Journal Issue: C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English

References (12)

Metallic fast reactor fuels journal January 1997
Transient Testing of Nuclear Fuels and Materials in the United States journal October 2012
Behavior of mixed-oxide fuel elements during an overpower transient journal September 1993
Constituent redistribution in U–Pu–Zr fuel during irradiation journal April 2004
Irradiation behavior of metallic fast reactor fuels journal June 1992
Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory journal January 2015
Fuel-cladding interaction layers in irradiated U-ZR and U-PU-ZR fuel elements. report January 2006
An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques journal October 2014
Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests journal December 1990
A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly design journal June 2009
Metal Fuel book January 2012
Temperature gradient driven constituent redistribution in UZr alloys journal January 1996