Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel-Reference-Cited by-同舟云学术

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

Published:2002-08 Issue:2-3 Volume:304 Page:221-236
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Meyer M.K,Hofman G.L,Hayes S.L,Clark C.R,Wiencek T.C,Snelgrove J.L,Strain R.V,Kim K.-H

Publisher

Elsevier BV

Subject

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

Reference43 articles.

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

3. Proceedings of the 20th International Meeting on Reduced Enrichment for Research and Test Reactors, Argonne National Laboratory Report ANL/TD/TM99-06;Durand,1999

4. Coextrusion of 60 to 30 wt% U3O8 Nuclear Fuel Elements, DPST-80-447;Peacock,1980

5. Irradiation behavior of high uranium-density alloys in the plate fuels

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