STUDY OF MODIFIED ZIRCONIUM ALLOYS CLADDINGS AFTER IRRADIATION
The in-pile tests and post-irradiation examinations offuel rods with claddings from E635M (Zr - 0.8Nb - 0.8Sn - 0.3Fe), E635opt (Zr - 0.8Nb - 1Sn - 0.3Fe) and E635M1 (Zr - 0.8Nb - 0.65Sn - 0.3Fe) zirconium alloys were carried out. Our objective was to study behavior (mainly corrosion including hydrogen pick-up and strengthening) of modified zirconium alloys claddings under irradiation compared to master alloy E635. E635M and E635opt alloys showed their prospects for use as cladding for fuel rods with enhanced characteristics.