Ceramic Fuel–Cladding Interaction

Author:

Maeda Koji

Publisher

Elsevier

Reference271 articles.

1. Fundamental Aspects of Nuclear Reactor Fuel Elements. TID-26711-P1;Olander,1976

2. Some aspects of the effects of fission fragment irradiation upon the oxidation of austenitic stainless steels by oxygen at 650° and 800 °C

3. Adamson, M.G., 1977. Proceedings of the International Working Group on Fast Reactors, Technical Committee Meeting on Fuel and Cladding Interaction, IWGFR/16, Tokyo, Japan, February 21–25, 1977, pp. 170–189. Austria: IAEA.

4. Adamson, M.G., Aitken, E.A., Caputi, R.W., Potter, P.E., Mignanelli, M.A., 1980. Proceedings of an International Symposium on Thermodynamics of Nuclear Materials, Jülich, January 29 to February 2, 1979, vol. I, pp. 503–538. Vienna, Austria: IAEA.

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