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- W64496662 abstract "Information is presented on hydrogen absorption in zirconium alloys, as revealed by six irradiation tests of purposely defected, Zircaloy-clad, UO/sub 2/ fuel elements. Both Zircaloy-2 and Zircaloy-4 (nickel-free Zircaloy-2) were used as cladding materials. ResuIts of these tests indicate that Zircaloy-4 has a much higher resistance to hydriding than does Zircaloy-2. (auth)" @default.
- W64496662 created "2016-06-24" @default.
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- W64496662 date "1961-08-01" @default.
- W64496662 modified "2023-09-27" @default.
- W64496662 title "HYDRIDING IN PURPOSELY DEFECTED, ZIRCALOY-CLAD FUEL RODS" @default.
- W64496662 hasPublicationYear "1961" @default.
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