1[1]Sabol,G.P.,et al," In reactor ccorrosion performance of Zirlo and Zircaloy-4",Zirconium in the Nuclear Industry:Tenth International Symposium,ASTM STP 1245,A.M.Garde and E.R.Bradley,Eds.,American Society for Testing and Materials, West Conshohocken, PA, 1994 PP.724~744
2[2]Mardon,J.P.,et al, "Development of New Zirocnium Alloys for PWR Fuel Rod Cladding",ANS West Palm Beach,April, 1994,PP.643 ~650
3[3]Nikulina, A.V.,et al,"Zirconium Alloy E635 as a Material for Fuel Rod Cladding and other components of VVER and other components of VVER and RBNK Cores", Zirconiun in the Nuclear Industry Eleventh Intemational Symposium, ASTM STP 1295,E.R..Bradley and G.P.-Sabol, Eds., American Society for Testing and Materials,1996, PP.785~804
4[7]Gazarolli,G.,et al,"Microstructure and corrosion studies for optimized PWR and BWR Zircaloy cladding",in Zirconium in the Nuclear Industry:Eighth International Symposium ASTM STP 1023, American Society for Testing and Materials, Philadelphia,1989,PP202-212
5[8]Garzarolli,F.,et al"Influence of various additions to water on Zircaloy-4 corrosion in Autoclave Tests at 350℃ in Proceeding of IAEA Technical commitee Meeting on Fundametal Aspects of corrosion of Zirconium-base Alloys in water Reactor Environments" IAEA, Vienna, 1990, IWGFPT/34, ISSN 1011-2766