Development, preparation and characterization of uranium molybdenum alloys for dispersion fuel application

Author:

Sinha V.P.,Prasad G.J.,Hegde P.V.,Keswani R.,Basak C.B.,Pal S.,Mishra G.P.

Publisher

Elsevier BV

Subject

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

Reference14 articles.

1. U-Si and U-Si-Ai Dispersion Fuel Alloy Development for Research and Test Reactors

2. J.P. Durand, Y. Lavastre, M. Grasse, Proceedings of the 20th International Meeting on Reduced Enrichment for Research and Test Reactors, Argonne National Laboratory Report ANL/TD/TM99-06, 1999, p. 28.

3. H.B. Peacock, Coextrusion of 60 to 30wt.% U3O8 Nuclear Fuel Elements, DPST-80-447, E.I. du Pont de Nemours and Company, 1980.

4. Irradiation behavior of high uranium-density alloys in the plate fuels;Ugajin;J. Nucl. Mater.,1998

5. Irradiation behavior of U6Mn-Al dispersion fuel elements;Meyer;J. Nucl. Mater.,2000

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