Corrosion release behavior of alloy 690 and its application in high-temperature water with Zn injection
0
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditionsof injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn injection, resulting in a better corrosion resistance. In comparisonwith the Zn-free condition, the corrosion release rate under the Zn-injection conditions was smaller. Thecorrosion release inhibiting factors were 1.7 and 1.9 under the conditions of 10 ppb and 50 ppb Zninjectionrespectively. A foreseen application of the corrosion and corrosion release rates has beenproposed and discussed.
Abstract
Corrosion release behavior of Alloy 690 in high-temperature water was investigated under the conditionsof injected Zn concentrations of 0 ppb, 10 ppb and 50 ppb. A protective oxide film composed of Zn(FexCr1-x)2O4 and Cr2O3 was formed with Zn injection, resulting in a better corrosion resistance. In comparisonwith the Zn-free condition, the corrosion release rate under the Zn-injection conditions was smaller. Thecorrosion release inhibiting factors were 1.7 and 1.9 under the conditions of 10 ppb and 50 ppb Zninjectionrespectively. A foreseen application of the corrosion and corrosion release rates has beenproposed and discussed.
참고문헌 (29)
- J. J. Kai, "The effects of heat-treatment on the carbide evolution and the chromium depletion along grain-boundary of Inconel-690 Alloy", Scripta, Metall. Mater, 23, pp.17~22 (1989)
- S. J. Zinkle, "Materials challenges in nuclear energy", Acta Mater, 61, pp.735~758 (2013)
- I. Chung, "An experimental study on fretting wear behavior of crosscontacting Inconel 690 tubes", Nucl. Eng. Des, 241, pp.4103~4110 (2011)
- PWR Axial Offset Anomaly (AOA) Guidelines, , EPRI, ~, pp.EPRI report TR-110070 (1999)
- 서승진, "BOTANI: High-fidelity Multiphysics Model for Boron Chemistry in CRUD Deposits", Nuclear Engineering and Technology, 53(5), pp.1676~1685 (2021), 한국원자력학회[DOI]
- M.W. Daniel, "NPC Conference", ~ (2016)
- D. Jeff, , JOM, 63, pp.64~72 (2011)
- B. Beverskog, "The role of zinc in LWRs", Int. Conf. On Water Chemistry of Nuclear Reactor Systems (2004)
- J. S. Choi, "Effect of zinc injection on the corrosion products in nuclear fuel assembly", Nat. Sci, 5, pp.173~181 (2013)
- W.A. Byers, "Structure and Chemistry of PWR Crud", Nuclear Plant Chemistry Conference (2006)
- J. J. Chen, "Characterization of interfacial reactions and oxide films on 316L stainless steel in various simulated PWR primary water environments", J. Nucl. Mater, 489, pp.137~149 (2017)
- G. D. Han, "Properties of oxide films formed on 316L SS and model alloys with modified Ni, Cr and Si contents in high temperature water", Corrosion Sci, 106, pp.157~171 (2016)
- Pressurized Water Reactor Zinc Application Data Analysis and Evaluation of Primary Chemistry Responses, , EPRI, ~, pp.EPRI report TR-1021111 (2010)
- H. Kawamura, , Corrosion Sci, 56, pp.623~637 (2000)
- Zinc Acetate Impact on AOA, , EPRI, ~, pp.EPRI report TR-1001396 (2001)
- J. B. Huang, "Influence of Zn on oxide films on Alloy 690 in borated and lithiated high temperature water", Corrosion Sci, 53, pp.3254~3261 (2011)
- Z. Y. Hai, "Research development of zinc water chemistry in PWRs", Corrosion Protect, 39, pp.539~543 (2018)
- X. H. Liu, "Status and progress on study of corrosion behavior of structure materials in Zn-injection waters for LWRs", Corrosion Sci. Protect. Technol, 23, pp.287~292 (2011)
- S. E. Ziemniak, "Zinc treatment effects on corrosion behavior of Alloy 600 in high temperature hydrogenated water", Corrosion Sci, 48, pp.3330~3348 (2006)
- Procedures for Quantitative Removal of Oxide Scales Formed in High Temperature Water and Steam, , NACE, ~, pp.NACE T-7D-167
- B. Stellwag, "The mechanism of oxide film formation on austenitic stainless steels in high temperature water", Corrosion Sci, 40, pp.337~370 (1998)
- M. Loïc, "Corrosion of nickel-base alloys in primary medium of pressurized water reactors : new insights on the oxide growth mechanisms and kinetic modellin", Corrosion Sci, 102, pp.24~35 (2016)
- X. D. Lin, "Corrosion of phase and phase boundary in proton-irradiated 308L stainless steel weld metal in simulated PWR primary water", Corrosion Sci, 165, pp.108401~ (2020)
- F. Q. Ning, "Effects of 405 stainless steel on crevice corrosion behavior of Alloy 690 in high-temperature pure water", J. Mater. Sci. Technol, 47, pp.76~87 (2020)
- J. P. Liao, "Fretting corrosion fatigue of Alloy 690 in high-temperature pure water", Corrosion Sci, 133, pp.423~431 (2018)
- W. J. Kuang, "The mechanism of oxide film formation on Alloy 690 in oxygenated high temperature water", Corrosion Sci, 53, pp.3853~3860 (2011)
- F. Q. Ning, "Crevice corrosion behavior of Alloy 690 in hightemperature water", J. Nucl. Mater, 515, pp.326~337 (2019)
- C. C. Lin, "Effects of hydrogen water chemistry on radiation field buildup in BWRs", Nucl. Eng. Des, 166, pp.31~36 (1996)
- Y. Takeda, "In situ and ex situ characterisation of oxide films formed on strained stainless steel surfaces in high-temperature water", Appl. Surf. Sci, 252, pp.8580~8588 (2006)
