共 26 条
- [1] LIU J L, HE G Z, CALLOW A, Et al., The Role of Β-Zr in a Zr-2.5Nb Alloy during Aqueous Corrosion: A Multi-Technique Study, Acta Materialia, 215, (2021)
- [2] LIU J K, STEINBRUCK M, GROssE M, Et al., Systematic Investigations on the Coating Degradation Mechanism during the Steam Oxidation of Cr-Coated Zry-4 at 1 200 ℃, Corrosion Science, 202, (2022)
- [3] LIU J L, YU H B, KARAMCHED P, Et al., Mechanism of the Α-Zr to Hexagonal-ZrO Transformation and Its Impact on the Corrosion Performance of Nuclear Zr Alloys, Acta Materialia, 179, pp. 328-341, (2019)
- [4] MOOREHEAD M, YU Z F, BORREL L, Et al., Comprehensive Investigation of the Role of Nb on the Oxidation Kinetics of Zr-Nb Alloys, Corrosion Science, 155, pp. 173-181, (2019)
- [5] SAINI S, GAYATHRI N, SHARMA S K, Et al., Microstructural Investigation of Irradiation Damage Behavior of Proton Irradiated Zr-1 wt.% Nb Fuel Cladding Alloy, Journal of Nuclear Materials, 528, (2020)
- [6] BAEK J H, PARK K B, JEONG Y H., Oxidation Kinetics of Zircaloy-4 and Zr-1Nb-1Sn-0.1Fe at Temperatures of 700–1 200 ℃, Journal of Nuclear Materials, 335, 3, pp. 443-456, (2004)
- [7] ALAT E, MOTTA A T, COMSTOCK R J, Et al., Multilayer (TiN, TiAlN) Ceramic Coatings for Nuclear Fuel Cladding, Journal of Nuclear Materials, 478, pp. 236-244, (2016)
- [8] CHENG B, KIM Y J, CHOU P., Improving Accident Tolerance of Nuclear Fuel with Coated Mo-Alloy Cladding, Nuclear Engineering and Technology, 48, 1, pp. 16-25, (2016)
- [9] LIU J K, CUI Z X, HAO Z, Et al., Steam Oxidation of Cr-Coated Sn-Containing Zircaloy Solid Rod at 1 000 ℃, Corrosion Science, 190, (2021)
- [10] MAIER B R, GARCIA-DIAZ B L, HAUCH B, Et al., Cold Spray Deposition of Ti<sub>2</sub>AlC Coatings for Improved Nuclear Fuel Cladding, Journal of Nuclear Materials, 466, pp. 712-717, (2015)