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Pore growth in U-Mo/Al dispersion fuel

  • Published:2016-09 Issue: Volume:478 Page:275-286
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Kim Yeon Soo,Jeong G.Y.ORCID,Sohn D.-S.,Jamison L.M.ORCID

Funder

U.S. Department of Energy

National Nuclear Security Administration

Korean government

Publisher

Elsevier BV

Subject

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

Reference51 articles.

1. Proc. Internat. Mtg. Reduced Enrichment for Research and Test Reactors (RERTR), Chicago, IL, USA, Oct. 5-10;Hofman,2003

2. Trans. Internat. Topical Meeting Research Reactor Fuel Management (RRFM), Munich, Germany, Mar. 21-24;Lemoine,2004

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

4. Trans. Internat. Topical Meeting Research Reactor Fuel Management (RRFM), Vienna, Austria, Mar. 22-25;Golosov,2009

5. Fission product induced swelling of U–Mo alloy fuel

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