Potential annealing treatments for tailoring the starting microstructure of low-enriched U–Mo dispersion fuels to optimize performance during irradiation

Author:

Keiser Dennis D.,Jue Jan-Fong,Woolstenhulme Nicolas E.,Ewh Ashley

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference13 articles.

1. Development of very-high-density low-enriched-uranium fuels

2. Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel

3. Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuel

4. D.D. Keiser Jr., J.-F. Jue, A.B. Robinson, M.R. Finlay, in: Proc. of Global 2009 International Conference on the Nuclear Fuel Cycle: Sustainable Options & Industrial Perspectives, Paris, France, September 6–11, 2009.

5. Microstructural characterization of U–7Mo/Al–Si alloy matrix dispersion fuel plates fabricated at 500°C;Keiser;J. Nucl. Mater.,2011

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