|
|
|
| Corrosion of Electrode Materials in Joule Heated Melter |
ZHANG Keqian, ZHANG Hua( ), LI Yang, HONG Ye, HE Cheng |
| China Institute of Atomic Energy, Beijing 102413, China |
|
|
|
|
Abstract The corrosion of ceramic furnace electrode materials in molten glass is discussed from three aspects: material, temperature and applied current. The results show that Inconel 693 forms an Al2O3 scale in molten glass. The corrosion resistance of Inconel 693 is better than that of Inconel 690. With the change of temperature, the corrosion rate of the material is determined by the Cr diffusion rate inside the material and the Cr2O3 dissolution rate on the surface. In the presence of electric current, the passive film of Inconel alloy in molten glass is destroyed and its corrosion resistance becomes poor. It is also suggested that the corrosion behavior and the relevant corrosion mechanism of materials should be investigated in combination with the practical operation conditions of JHM in the future.
|
|
Received: 26 May 2021
|
|
|
|
Corresponding Authors:
ZHANG Hua
E-mail: zhanghua_32@ciae.ac.cn
|
About author: ZHANG Hua, E-mail: zhanghua_32@ciae.ac.cn
|
| 1 |
Ojovan M I. Handbook of Advanced Radioactive Waste Conditioning Technologies [M]. Cambridge: Woodhead Publishing, 2011
|
| 2 |
Li Y S, Zhang S D, Xian L, et al. Progress in research and development of vitrification technology for high-level radioactive liquid waste at CIAE [J]. At. Energy Sci. Technol., 2020, 54: 126
|
|
李玉松, 张生栋, 鲜亮等. CIAE高放废液固化技术研发进展 [J]. 原子能科学技术, 2020, 54: 126
|
| 3 |
Zhang W, Dong H L, Ruan M Z. Applicability analysis of ceramic melter technology in vitrification of high level radioactive liquid waste from spent fuel reprocessing of nuclear power plants [J]. Radiat. Prot., 2019, 39: 322
|
|
张威, 董海龙, 阮苠秩. 陶瓷电熔炉在动力堆高放废液玻璃固化中适用性分析 [J]. 辐射防护, 2019, 39: 322
|
| 4 |
Sengupta P, Mittra J, Kale G B. Interaction between borosilicate melt and Inconel [J]. J. Nucl. Mater., 2006, 350: 66
|
| 5 |
Hsu J H, Newkirk J W, Kim C W, et al. Corrosion of Inconel 690 and Inconel 693 in an iron phosphate glass melt [J]. Corros. Sci., 2013, 75: 148
|
| 6 |
Giggins C S, Pettit F S. Oxidation of Ni‐Cr‐Al alloys between 1000 ℃ and 1200 ℃ [J]. J. Electrochem. Soc., 1971, 118: 1782
|
| 7 |
Maruyama T, Ani M H B, Ueda M, et al. Quantitative evaluation of the effect on the Al addition on the internal-external oxidation in Ni-Cr alloys [A]. Proceedings of High Temperature Corrosion and Materials Chemistry: Proceedings of the International Symposium [C]. New Jersey, 2003: 96
|
| 8 |
Campbell F C. ASM Handbook: Alloy Phase Diagrams [M]. Materials Park: ASM International, 2012
|
| 9 |
Sims C T. Niobium in superalloys: A perspective [J]. High Temp. Technol., 1984, 4: 185
|
| 10 |
Natesan K, Baxter D J. Stability of chromium oxide scales in oxygen-sulfur containing environments at elevated temperatures [A]. Proceedings of TMS-AIME Fall Meeting [C]. Detroit, 1984: 237
|
| 11 |
Zhu D M, Kim C W, Day D E. Corrosion behavior of Inconel 690 and 693 in an iron phosphate melt [J]. J. Nucl. Mater., 2005, 336: 47
|
| 12 |
Halder R, Sengupta P, Abraham G, et al. Interaction of alloy 693 with borosilicate glass at high temperature [J]. Mater. Today, 2016, 3: 3025
|
| 13 |
Chen T F, Tiwari G P, Iijima Y, et al. Volume and grain boundary diffusion of chromium in Ni-base Ni-Cr-Fe alloys [J]. Mater. Trans., 2003, 44: 40
|
| 14 |
Chen T F, Iijima Y, Hirano K I, et al. Diffusion of chromium in nickel-base Ni-Cr-Fe alloys [J]. J. Nucl. Mater., 1989, 169: 285
|
| 15 |
Tan T C, Chin D T. A.c. corrosion of nickel in sulphate solutions [J]. J. Appl. Electrochem., 1988, 18: 831
|
| 16 |
Wendt J L, Chin D T. The a.c. corrosion of stainless steel-II. The breakdown of passivity of ss304 in neutral aqueous solutions [J]. Corros. Sci., 1985, 25: 889
|
| 17 |
Gan H, Buechele A C, Kim C W, et al. Corrosion of Inconel-690 electrodes in waste glass melts [J]. MRS Online Proc. Libr., 1999, 556: 287
|
| 18 |
Hsu J H, Newkirk J W, Kim C W, et al. The performance of Inconel 693 electrodes for processing an iron phosphate glass melt containing 26 wt.% of a simulated low activity waste [J]. J. Nucl. Mater., 2014, 444: 323
|
| 19 |
Dutta R S, Bhandari S, Chakravarthy Y, et al. Development of aluminide coatings on Ni-Cr-Fe based superalloy 690 substrates for high temperature applications using atmospheric plasma spraying technique [J]. Mater. Today, 2016, 3: 3018
|
| 20 |
Dharini T, Kuppusami P, Panda P, et al. Nanomechanical behaviour of Ni-YSZ nanocomposite coatings on superalloy 690 as diffusion barrier coatings for nuclear applications [J]. Ceram. Int., 2020, 46: 24183
|
| 21 |
Yusufali C, Kshirsagar R J, Jagannath, et al. Surface studies on aluminized and thermally oxidized Alloy 690 substrates interacted with nitrate-based simulated nuclear waste and sodium borosilicate melt using Raman spectroscopy and X-ray photoelectron spectroscopy [J]. Surf. Coat. Technol., 2015, 266: 31
|
| 22 |
Dutta R S, Yusufali C, Paul B, et al. Formation of diffusion barrier coating on superalloy 690 substrate and its stability in borosilicate melt at elevated temperature [J]. J. Nucl. Mater., 2013, 432: 72
|
| No Suggested Reading articles found! |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
| |
Shared |
|
|
|
|
| |
Discussed |
|
|
|
|