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- W1559463583 abstract "did not appear to vary appreciably with minor changes in Zr or fissium content. Decreasing the Pu to 10 wt%, however, significantly improved the swelling behavior of the alloy. Both pourcast and thermally cycled material and pour-cast, extruded, and thermally cycled material appeared to be more stable under irradiation than injection-cast material. Under comparable irradiation conditions, the specimens of U-20 wt% Pu- 5 wt% Mo alloy were less dimensionally stable than the U-Pu-fissium alloys investigated. (auth)" @default.
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- W1559463583 date "1971-01-01" @default.
- W1559463583 modified "2023-10-15" @default.
- W1559463583 title "IRRADIATION BEHAVIOR OF URANIUM-FISSIUM ALLOYS. EBR-II Project." @default.
- W1559463583 doi "https://doi.org/10.2172/4681208" @default.
- W1559463583 hasPublicationYear "1971" @default.
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