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Title: Pore growth in U-Mo/Al dispersion fuel

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC-02-06CH11357; NA-23
OSTI ID:
1325332
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 478 Journal Issue: C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English
Citation Metrics:
Cited by: 13 works
Citation information provided by
Web of Science

References (31)

In-pile test results of U-silicide or U-nitride coated U-7Mo particle dispersion fuel in Al journal November 2014
Fission product release from trace irradiated UO2+x journal March 1998
U–Mo/Al–Si interaction: Influence of Si concentration journal April 2010
REVIEW OF 15 YEARS OF HIGH-DENSITY LOW-ENRICHED UMo DISPERSION FUEL DEVELOPMENT FOR RESEARCH REACTORS IN EUROPE journal April 2014
Improved Irradiation Performance of Uranium-Molybdenum/Aluminum Dispersion Fuel by Silicon Addition in Aluminum journal October 2013
Influence of Fuel-Matrix Interaction on the Breakaway Swelling of u-mo Dispersion fuel in al journal April 2014
Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuel journal April 2008
DART Analysis of Irradiation Behavior of U-Mo/Al Dispersion Fuels journal July 2015
Irradiation behavior of the interaction product of U-Mo fuel particle dispersion in an Al matrix journal June 2012
Fuel swelling and interaction layer formation in the SELENIUM Si and ZrN coated U(Mo) dispersion fuel plates irradiated at high power in BR2 journal March 2015
From High to Low Enriched Uranium Fuel in Research Reactors journal October 2010
Surface free energies of solid metals: Estimation from liquid surface tension measurements journal January 1977
Fission-enhanced diffusion in dispersion fuels journal January 2008
Mechanical analysis of UMo/Al dispersion fuel journal November 2015
Surface engineering of low enriched uranium–molybdenum journal September 2013
Modeling a failure criterion for U–Mo/Al dispersion fuel journal May 2016
Transmission electron microscopy characterization of irradiated U–7Mo/Al–2Si dispersion fuel journal January 2010
Molecular dynamics simulations of α-alumina and γ-alumina surfaces journal September 1993
Use of a Centrifugal Atomization Process in the Development of Research Reactor fuel journal October 2007
Chapter 1 Solids in Contact journal November 1986
The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide journal June 1982
Assessment of effective thermal conductivity in U–Mo metallic fuels with distributed gas bubbles journal July 2015
Amorphization of the interaction products in U–Mo/Al dispersion fuel during irradiation journal April 2009
A Theory for the Estimation of Surface and Interfacial Energies. I. Derivation and Application to Interfacial Tension journal July 1957
Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuel journal October 2004
Wetting of molten Bi–Sn alloy on amorphous Fe78B13Si9 journal May 2008
Recrystallization and fission-gas-bubble swelling of U–Mo fuel journal May 2013
Radiation enhanced diffusion in UO 2 and (U, Pu)O 2 journal January 1983
MODELING OF INTERACTION LAYER GROWTH BETWEEN U-Mo PARTICLES AND AN Al MATRIX journal December 2013
Fission product induced swelling of U–Mo alloy fuel journal December 2011
Fission induced swelling of U–Mo/Al dispersion fuel journal October 2015

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