Abstract
Embrittlement of Zircaloy fuel cladding tubes by corrosion media was studied from the viewpoint of its applicability to spent-fuel reprocessing. The results from irradiated as well as unirradiated tubes are summarized as follows: (1) when iodine was employed as the solute, the use of methanol as the solvent caused significant embrittlement of the Zircaloy; (2) for the iodine-methanol solution, the embrittlement increased with the iodine content but saturated at 1 wt%; (3) a water content of up to 10 vol% in the iodine-methanol solution did not decrease the extent of embrittlement; (4) fracture was of the grain-boundary type, and a fuel cladding tube irradiated to [approximately] 35GWd/t showed the same embrittlement behavior as an unirradiated one.
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