Corrosion Behavior of Chromium Oxide Based Ceramics in Supercritical Water Environments
The Super Critical Water-cooled Reactor (SCWR) has been proposed as one of the most promising reactor concepts and is currently considered by some countries as the next generation nuclear energy reactor. Extensive investigations have been conducted to study the corrosion behavior of various candidate materials exposed to SCW conditions, since identifying suitable structural materials is one of the key issues for developing the SCWR. Ceramic materials have been considered for specific applications in SCWR, such as coating and insulation, owing to their unique corrosion-resistance compared to metallic materials. In this study, chromium oxide (Cr2O3) based ceramics prepared by different sintering process were exposed to various SCW environments by employing both static and fluid SCW autoclave facilities. Different amounts of additives such as Y2O3 and yttria stabilized zirconia (YSZ- 8 mol ％ Y2O3), were added to the initial powders to examine their effects on the stability of the Cr2O3 based ceramics obtained under SCW conditions. Some SCW testing variables, especially the oxygen concentration, were varied during the tests and were found to influence the corrosion behavior of the ceramics. The results show that the stability of the chromium oxide based ceramics was affected by their structure as well as the dissolved oxygen concentration. Partial disintegration was observed for porous chromium oxide coupons exposed to SCW at 625°C. Addition of yttria (5 wt. ％) or YSZ (20 wt. ％) increased the stability of the porous oxide. The SCW loop tests show that the porous chromium oxide based ceramics were stable and retained their physical integrity under SCW conditions at 650°C with low to moderate oxygen concentration (8 ppb and 8 ppm). However, these ceramics suffered from degradation when exposed to SCW with higher oxygen concentrations (4 vol. ％ hydrogen peroxide) because of the formation of soluble Cr6+ species.
Ziqiang Dong Weixing Chen Wenyue Zheng Dave Guzonas
Department of Chemical and Materials Engineering,University of Alberta,Edmonton,Canada MTL-NRCan,568 Booth Street,Ottawa,Canada Chalk River Laboratories,Atomic Energy of Canada Limited,Chalk River,Canada
国际会议
3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)
西安
英文
1-10
2012-04-18（万方平台首次上网日期，不代表论文的发表时间）