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)