PWR water corrosion and high temperature steam oxidation behavior of surface-modified Zircaloy and FeCrAl coated Mo alloy developed for accident tolerant fuel cladding
Under the framework of the China accident tolerant fuels(ATF)research project led by China General Nuclear Power Corporation(CGN),surface-modified Zircaloy and oxide dispersion strengthened(ODS)Mo cladding have been developed for further enhancing accident tolerance of light water reactors(LWRs).In order to improve corrosion and oxidation resistance,NiCrAl coating was selected as a preliminary trial for Zircaloy cladding(Zr-1Nb),while FeCrAl was adopted for ODS Mo cladding.These coated materials were tested in simulated PWR water and loss of coolant accident(LOCA)condition to evaluate the compatibility of the coatings with the extreme environments.The results show that the NiCrAl coating on Zircaloy has some defects like small pores and microcracks,but its oxidation resistance was not negatively affected,showing much lower oxidation rate than the coating-free Zircaloy exposed to water steam at 1200℃.The FeCrAl coating was not subjected to severe corrosion after exposed to PWR water at 360℃ and 18.6MPa for 72h.Furthermore,no obvious mass changes and exfoliations occurred to the coating after the simulated LOCA test.This indicates that the FeCrAl coating is highly adherent to the Mo substrate.The excellent corrosion and oxidation resistance of the two coatings can be attributed to formation of a protective thin Al2O3 film that is an effective barrier against atomic diffusion.
Surface-modified Zircaloy ODS Mo alloy Accident tolerant fuels (ATF) Coating Corrosion Oxidation
Xing Gong Jiaxiang Xue Rui Li Sigong Li Jun Yan Qisen Ren Tong Liu*
Department of ATF R&D,China Nuclear Power Technology Research Institute Co.,Ltd.,China General Nuclear Power Corporation(CGN),Shenzhen,518026,China
国际会议
沈阳
英文
120-128
2017-09-26（万方平台首次上网日期，不代表论文的发表时间）