Engineering of Fuel Plates on Uranium-Molybdenum Monolithic: Critical Issues
Open Access
- 1 January 2015
- journal article
- research article
- Published by Scientific Research Publishing, Inc. in World Journal of Nuclear Science and Technology
- Vol. 05 (04), 274-286
- https://doi.org/10.4236/wjnst.2015.54027
Abstract
Engineering of nuclear fuels using monolithic plates of uranium-molybdenum and Al-6061 cladding is the current challenge for research and test reactors. The main drawback of the manufacture of monolithic nuclear fuel was analyzed using two surface coating methods: aluminum sputtering and transient liquid phase bonding (TLPB). Coating was done with a commercial alloy of Al-Si (R-4047). These techniques were used to improve the metallurgical bonding between the UMo and the cladding by rolling. Finally, design parameters and manufacture of UMo plate fuels were established. Mechanical tests were used to characterize the plates, resulting in UTS values of about 700 and 1000 MPa for the UMo alloys. These results are complemented with metrological analyses, X-Ray diffraction (XRD), thermal analyses, and metallography. X-rays and ultrasound scanners were used to monitor bonding and the co-rolling effects. These initial results show the main obstacles to the engineering development of UMo monolithic plate fuels with Al-6061 cladding, and these are discussed herein.Keywords
This publication has 15 references indexed in Scilit:
- Effect of molybdenum addition on metastability of cubic γ-uraniumJournal of Alloys and Compounds, 2010
- Development, preparation and characterization of uranium molybdenum alloys for dispersion fuel applicationJournal of Alloys and Compounds, 2009
- Transmission electron microscopy investigation of irradiated U–7wt%Mo dispersion fuelJournal of Nuclear Materials, 2008
- Thermophysical Properties of U–Mo/Al Alloy Dispersion Fuel MeatsInternational Journal of Thermophysics, 2007
- An interdiffusional model for prediction of the interaction layer growth in the system uranium–molybdenum/aluminumJournal of Nuclear Materials, 2007
- Heats of formation of (U,Mo)Al3 and U(Al,Si)3Journal of Nuclear Materials, 2006
- Phase development in Al-rich U–Mo–Al alloysScripta Materialia, 2004
- High-density U-Mo fuel for research reactorsMetal Science and Heat Treatment, 2004
- Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuelJournal of Nuclear Materials, 2004
- High-density, low-enriched uranium fuel for nuclear research reactorsJOM, 2003