Dilworth & Barrese
Composition of zirconium alloy having high corrosion resistance and high strength
 The invention presented herein relates to a zirconium alloy with superior corrosion resistance and high strength for use in fuel rod claddings, spacer grids and structural components as used in reactor core of light water and heavy water nuclear power plant. The zirconium alloy of this invention with superior corrosion resistance and high strength comprises an alloy composition as follows: PA1 niobium(Nb), in a range of 0.05 to 0.3 wt. %; PA1 tin(Sn), in a range of 0.8 to 1.6 wt. %; PA1 iron(Fe), in a range of 0.2 to 0.4 wt. %; PA1 a selected one from the group consisted of vanadium(V), tellurium(Te), antimony(Sb), molybdenum(Mo), tantalum(Ta), and copper(Cu), in a range of 0.05 to 0.20 wt. %; PA1 oxygen(O), in a range of 600 to 1400 ppm; and PA1 the balance being zirconium(Zr). 
Korea Electric Power Corporation Korea Atomic Energy Research Institute
C
C22C
inventional
Jong Hyuk Kyeong Ho Youn Ho Yong Hwan Byong Kwon Sun Jae Il Hiun
Baek Kim Jung Jeong Choi Kim Kuk