Author:
Ryu Ho Jin,Kim Yeon Soo,Hofman Gerard L.,Park Jong Man,Kim Chang Kyu
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference10 articles.
1. Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel
2. Post-irradiation examination of uranium–7wt% molybdenum atomized dispersion fuel
3. Irradiation behaviour of UAlx-Al dispersion fuels for thermal high flux reactors
4. L.S. DeLuca, H.T.Sumsion, KAPL-1747, Knolls Atomic Power Labvoratory, 1957.
5. Y.S. Kim, G.L. Hofman, H.J. Ryu, J. Rest, in: Proceedings of the 27th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Boston, USA, 2005. Available from: .
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