Thermodynamic modeling of Al–U–X (X = Si,Zr)-Reference-Cited by-同舟云学术

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Thermodynamic modeling of Al–U–X (X = Si,Zr)

Published:2015-09 Issue: Volume:464 Page:170-184
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Rabin Daniel,Shneck Roni Z.,Rafailov Gennady,Dahan Isaac,Meshi Louisa,Brosh Eli

Publisher

Elsevier BV

Subject

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

Reference56 articles.

1. G. Hofman, A short note on high density dispersion fuel, Argonne National Laboratory, 1996 .

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

3. Test irradiations of full-sized U3Si2–Al fuel plates up to very high fission densities

4. Microstructural analysis of as-processed U–10wt.%Mo monolithic fuel plate in AA6061 matrix with Zr diffusion barrier

5. Effect of Si and Zr on the interdiffusion of U–Mo alloy and Al

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1. From caged compounds with isolated U atoms to frustrated magnets with 2- or 3-atom clusters: a review of Al-rich uranium aluminides with transition metals;Reports on Progress in Physics;2024-02-06

2. Experimental determination of phase equilibria and phase stability in the Al-U system by using DSC, spot-technique and XRD;Thermochimica Acta;2022-12

3. About the enthalpy of formation of the UZr2 compound;Journal of Nuclear Materials;2022-04

4. Pressure Tuned Structural, Electronic and Elastic Properties of U3Si2C2: A First Principles Study;Crystals;2021-11-20

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