| Title |
Corrosion Characteristics of New Zr - based Alloy for Nuclear Fuel Cladding |
| Authors |
정용환(Yong Hwan Jeong); 김창호(Chang Ho Kim) |
| Abstract |
Corrosion tests of various Zr-based alloys were performed at 350℃ in pure water and aqueous solution containing 220 ppm Li. The alloys were standard Zircaloy-4, Zirealoy type alloys(ZrSnFeCr), ZrNbFeCr, ZrSnNbFeCr and ZrFeCr alloys. For some of them Cr was replaced by V. In pure water Zircaloy-type alloys showed higher corrosion resistance than standard Zicaloy-4, while most Nb-containing alloys showed lower corrosion resistance. All of the alloys tested in this study exhibited the Li-accelerated corrosion in 220 ppm Li solution. The influence of Li addition on corrosion was small for the Zircaloy-type alloys, but significant for the Nb-containing alloys. Especially, C-2(Zr0.1Nb0.25Sn0.4Fe0.2Cr) which had superior corrosion resistance in water showed much higher corrosion rate in 220 ppm Li solution than 1.4Sn Zircaloy-type alloy(A-1). Addition of tin in the range of 0.8∼1.1wt% imparted good corrosion resistance to Zircaloy-type alloys in pure water and 220 ppm Li solution. The addition of 0.1∼0.4wC%Nb which is below the solubility limit in Zr matrix improved the corrosion resistance in low tin alloys. |