Migration of Metallic Fission Products in Reactor Oxide Fuels
Author:
Affiliation:
1. European Institute for Transuranium Elements EURATOM, D-Karlsruhe, P.O. Box 2266, Federal Republic of Germany
2. Institut für Neutronenphysik und Reaktortechnik Kernforschungszentrum Karlsruhe, Federal Republic of Germany
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT77-A31851
Reference19 articles.
1. Electron probe micro-analysis of irradiated UO2
2. Microanalysis of inclusions in irradiated UO2
3. Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron flux
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