Author:
Ishii Tetsuya,Asaga Takeo
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference8 articles.
1. MATERIAL TRANSPORT IN THE TEMPERATURE GRADIENT OF FAST REACTOR FUELS
2. Hj. Matzke, Non-Stoichiometric Oxide, Academic Press, New York, 1981, pp. 156–232 (Ch. 4)
3. Interdiffusion and chemical diffusion in the UO2 — (U,Pu)O2 system
4. T. Mizuno et al., in: International Conference on Reliable Fuels for Liquid Metal reactors, Tucson, AZ, 1986, p. 5
5. Plutonium redistribution in mixed oxide (U, Pu)O2 nuclear fuel elements
Cited by
19 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献