Abstract: In the process of fast reactor design and application, the zirconium hydride is a useful neutron moderator for fast reactor. However, there are few reports on the compatibility of the zirconium hydride in sodium at high temperature. And no data are available to support the application at high temperature sodium. As a result, the compatibility of the zirconium hydride in sodium was studied in this work. The ZrH1.8 was tested at 500 ℃, 600 ℃ and 700 ℃ in sodium. Another, some samples prepared with a ZrO2 layer were also tested at 650 ℃ in sodium to evaluate the capabi-lity of preventing hydrogen loss. The test results showed that a ZrO2 layer grew on the surface of zirconium hydride when it was tested at 500 ℃, 600 ℃ and 700 ℃ in sodium. There was no hydrogen emission of ZrH1.8 at 500 ℃. However, the hydrogen content decreased obviously after 120 h at 600 ℃ and 700 ℃. Moreover, a ZrO2 layer prepared for zirconium hydride could not prevent hydrogen loss after exposure at 650 ℃ in sodium. In the process of hydrogen emission at high temperature, due to the opposite movement of hydrogen and oxygen, ZrO2 transformed into Zr3O gradually at the ZrO2/ZrH1.8 interface.
付晓刚, 张金权, 秦博, 马浩然, 龙斌. 氢化锆与高温钠的相容性研究[J]. 材料导报, 2019, 33(11): 1801-1804.
FU Xiaogang, ZHANG Jinquan, QIN Bo, MA Haoran, LONG Bin. The Compatibility of Zirconium Hydride in a Sodium Environment. Materials Reports, 2019, 33(11): 1801-1804.
1 Mueller W M. Metal hydrides,Academic Press, USA,1968. 2 Tsuchiya B, Huang J, Konashi K, et al. Journal of Nuclear Materials,2001,289,329. 3 Terrani K A, Balooch M, Wongsawaeng D, et al. Journal of Nuclear Materials,2010,397,61. 4 Ponomarev-Stepnoi N N, Bubelev V G, Glushkov E S, et al. Atomic Energy,2007,102(2),87. 5 Olander D, Greenspan E, Garkisch H D, et al. Nuclear Engineering and Design,2009,239,1406. 6 Simnad M T. Nuclear Engineering and Design,1981,64,403. 7 Wang J W, Wang L J, Chen W D, et al. Chinese Journal of Rare Metals,2012,36(1),61(in Chinese). 王建伟,王力军,陈伟东,等.稀有金属,2012,36(1),61. 8 Zhang H F, Yang Q F, Wang Z D, et al. Atomic Energy Science and Technology,2005,39(suppl),83(in Chinese). 张华峰,杨启法,王振东,等.原子能科学技术,2005,39(增刊),83. 9 Xie J C, Zhao S Z, Jia B S, et al. Atomic Energy Science and Technology,2011,45(1),48(in Chinese). 解家春,赵守智,贾宝山,等.原子能科学技术,2011,45(1),48. 10 Naoyuki T, Tomoyasu M. In: International Conference on Global Environment and Advanced Nuclear Power Plants, Kyoto,2003,pp.1169. 11 Wang W E, Olander D R. Journal of the American Ceramic Society,1995,78(12),3323. 12 Barraclough K G, Beevers C J. Journal of Nuclear Materials,1970,34,125. 13 Forcey K S, Ross D K, Simpson J C B. Journal of Nuclear Materials,1988,160,117. 14 Ma H R, Fu X G, Qin B. Atomic Energy Science and Technology,2016,50(11),2023(in Chinese). 马浩然,付晓刚,秦博.原子能科学技术,2016,50(11),2023.
渝公网安备50019002502923号 版权所有：《材料导报》编辑部
2019, Vol. 33 
