Performance of iron-chromium-aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions

JOURNAL OF NUCLEAR MATERIALS

卷:470

Article

Zhong, Weicheng¹  Mouche, Peter A.¹  Han, Xiaochun¹  Heuser, Brent J.¹  Mandapaka, Kiran K.²  Was, Gary S.² 

[1] Univ Illinois, Dept Nucl Radiol & Plasma Engn, Urbana, IL 61801 USA

[2] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA

关键词: LWR cladding;    Oxidation;    Corrosion;    Protective coatings;    FeCrAl;    Alumina;   

DOI  :  10.1016/j.jnucmat.2015.11.037

来源: Elsevier

【 摘 要 】

Iron-chromium-aluminum (FeCrAl) coatings deposited on Zircaloy 2 (Zy2) and yttria-stabilized zirconia (YSZ) by magnetron sputtering have been tested with respect to oxidation weight gain in high-temperature steam. In addition, autoclave testing of FeCrAl-coated Zy2 coupons under pressure-temperature-dissolved oxygen coolant conditions representative of a boiling water reactor (BWR) environment has been performed. Four different FeCrAl compositions have been tested in 700 degrees C steam; compositions that promote alumina formation inhibited oxidation of the underlying Zy2. Parabolic growth kinetics of alumina on FeCrAl-coated Zy2 is quantified via elemental depth profiling. Autoclave testing under normal BWR operating conditions (288 degrees C, 9.5 MPa with normal water chemistry) up to 20 days demonstrates observable weight gain over uncoated Zy2 simultaneously exposed to the same environment. However, no FeCrAl film degradation was observed. The 900 degrees C eutectic in binary Fe-Zr is addressed with the FeCrAl-YSZ system. (C) 2015 Elsevier B.V. All rights reserved.

【 授权许可】

Free