Microstructure characterization of as-fabricated and 475°C annealed U–7wt.% Mo dispersion fuel in Al–Si alloy matrix-Reference-Cited by-同舟云学术

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Microstructure characterization of as-fabricated and 475°C annealed U–7wt.% Mo dispersion fuel in Al–Si alloy matrix

Published:2011-09 Issue:39 Volume:509 Page:9487-9496
ISSN:0925-8388
Container-title:Journal of Alloys and Compounds
language:en
Short-container-title:Journal of Alloys and Compounds

Author:

Yao Bo,Perez Emmanuel,Keiser Dennis D.,Jue Jan-Fong,Clark Curtis R.,Woolstenhulme Nicolas,Sohn Yongho

Publisher

Elsevier BV

Subject

Materials Chemistry,Metals and Alloys,Mechanical Engineering,Mechanics of Materials

Reference41 articles.

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

2. Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel

3. Irradiation behavior of atomized U–10wt.% Mo alloy aluminum matrix dispersion fuel meat at low temperature

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

5. Proceedings of International Meeting on PERTR;Hofman,2004

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1. Microstructure and microchemistry changes at U-10Mo fuel/AA6061 cladding interfaces with varying hot isostatic pressing conditions;Journal of Nuclear Materials;2023-11

2. Al-Mo-U Ternary Phase Diagram Evaluation;MSI Eureka;2019-11-12

3. Molecular dynamics simulations of displacement cascade and threshold energy in ordered alloy Al3U;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2019-06

4. Mechanical properties of irradiated U Mo alloy fuel;Journal of Nuclear Materials;2019-03

5. Fases identificables en la zona de interacción de placas combustibles dispersas U3Si2/Al;Matéria (Rio de Janeiro);2018-07-19

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