The Melt Refining of Irradiated Uranium: Application to EBR-II Fast Reactor Fuel. X. The Behavior of Zirconium
| Autor: | N. R. Chellew, V. G. Trice |
|---|---|
| Rok vydání: | 1961 |
| Předmět: |
Zirconium
Materials science 010308 nuclear & particles physics Zirconium alloy Metallurgy 0211 other engineering and technologies Oxide chemistry.chemical_element 02 engineering and technology Uranium 01 natural sciences chemistry.chemical_compound Cerium Nuclear Energy and Engineering chemistry 0103 physical sciences Cubic zirconia 021108 energy Carbon Refining (metallurgy) |
| Zdroj: | Nuclear Science and Engineering. 9:78-81 |
| ISSN: | 1943-748X 0029-5639 |
| DOI: | 10.13182/nse61-a25869 |
| Popis: | Melt refining experiments in which irradiated uranium or synthetic EBR- II alloys were melted in oxide crucibles showed that removal of zirconium as an oxide does not occur at temperatares up to 1400 ts C. Removal of zirconium by carbon scavenging of the melt was approximately 50% in 5-hr melts at 1400 ts C; the mechanism and products of reactions which led to this separation are discussed. Zirconium contamination of uranium- cerium alloys melted in limestabilized zirconia crucibles was negligible. (auth) |
| Databáze: | OpenAIRE |
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