Author(s)

Chao Sun, Zhongbo Yang, Zongpei Wu

Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, China.

Zr-Sn-Nb-Fe alloys are one of the important directions for continuous improvement of zirconium alloys for high burn-up fuel assemblies. The corrosion resistance of Zr-Sn-Nb-Fe alloys is closely related to the alloying element and water chemical condition. To better understand the effect of Sn on corrosion resistance of Zr-Sn-Nb-Fe alloy, the normal N36 (Zr-1Sn-1Nb-0.3Fe) and low-tin N36 (Zr-0.8Sn-1Nb-0.3Fe) alloy sheets were prepared and tested in static autoclave in both of 0.01 mol/L LiOH and 0.03 mol/L LiOH aqueous solution at 360°C and 18.6 MPa. The characteristics of the microstructure and oxide film of alloys were analyzed by TEM and SEM respectively. It was shown that that the corrosion transition of the normal N36 appears earlier and the weight gain is higher than the low-tin N36 in two corrosive mediums. The cracks paralleling to the interface of oxide/metal are formed in the fracture surface of the oxide film and the micrographs at the oxide film/substrate interface appear uneven morphology. With the increasing of corrosion gain, there are more parallel cracks in oxide film and the uneven morphology at the oxide film/substrate interface is more obvious.

N36 Zirconium Alloy, Corrosion, Oxide Films, Morphology

Sun, C. , Yang, Z. and Wu, Z. (2018) Study on Corrosion Resistance of N36 Zirconium Alloy in LiOH Aqueous Solution. World Journal of Nuclear Science and Technology, 8, 30-37. doi: 10.4236/wjnst.2018.82004.