Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel-Reference-Cited by-同舟云学术

Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel

Published:2017-04 Issue: Volume:487 Page:265-279
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Jeong G.Y.^ORCID,Kim Yeon Soo,Jamison L.M.^ORCID,Robinson A.B.,Lee K.H.,Sohn Dong-Seong

Funder

US DOE M3 program

Nuclear R&D program through the National Research Foundation of Korea (NRF)

Ministry of Science, ICT & Future Planning

U.S. Department of Energy, National Nuclear Security Administration (NNSA), Office of Material Management and Minimization (NA-23) Reactor Conversion Program

UChicago Argonne, LLC

Publisher

Elsevier BV

Subject

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

Reference54 articles.

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2. Proc. Int. Mtg. on Reduced Enrichment for Research and Test Reactors (RERTR), San Carlos de Bariloche, Argentina;Hofman,2002

3. Irradiation-enhanced interdiffusion in the diffusion zone of U-Mo dispersion fuel in Al

4. J. Rest, Proc. Int. Mtg. On Reduced Enrichment for Research and Test Reactors (RERTR), Beijing, China;Kim,2009

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