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Review on Corrosion Thickness Design of Canister for High-level Radioactive Waste in Japan |
PENG Liyuan1,2( ), XIE Jingli1,2, CAO Shengfei1,2, TAN Jibo3, WU Xinqiang3, ZHANG Ziyu3 |
1.Beijing Research Institute of Uranium Geology, Beijing 100029, China 2.High-level Radioactive Waste, CAEA Innovation Center for Geological Disposal, Beijing 100029, China 3.CAS Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China |
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Cite this article:
PENG Liyuan, XIE Jingli, CAO Shengfei, TAN Jibo, WU Xinqiang, ZHANG Ziyu. Review on Corrosion Thickness Design of Canister for High-level Radioactive Waste in Japan. Journal of Chinese Society for Corrosion and protection, 2025, 45(3): 563-576.
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Abstract The safe disposal of high-level radioactive waste is an international challenge. Deep geological disposal repository for high-level radioactive waste with multibarrier system design concept is being planned to construct in China to isolate the radionuclides from the biosphere. To meet the safe function of isolating waste from the biosphere, while also suppressing the release and migration of radionuclides into groundwater within its designed lifetime, the disposal canister, as the key engineering barriers, should maintain its integrity and avoid failure by corrosion. Thus, it is of great significance to design the corrosion allowance of the canister reasonably. Carbon steels are less susceptible to localized corrosion and mainly corrodes uniformly. The corrosion allowance is acquired by the corrosion rate and lifetime when carbon steels are adopted as materials for canister. The design concept of the corrosion allowance of the canister for high-level radioactive waste in Japan is reviewed in the present work. The possible corrosion forms and the corrosion thickness prediction models of the carbon steel canister in disposal repository are analyzed, and modification suggestions are also discussed, aiming to provide a reference for the corrosion thickness design of the canister.
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Received: 08 July 2024
32134.14.1005.4537.2024.205
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Fund: CAEA Innovation Center for Geological Disposal of High level Radioactive Waste(WDZC-2023-HDYY-102) |
Corresponding Authors:
PENG Liyuan, E-mail: 17824033690@163.com
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[1] |
Ishikawa H, Honda A, Tsurudome K, et al. Selection of candidate materials for overpack and life prediction of Carbon Steel overpack [R]. Ibaraki-ken: Japan Nuclear Cycle Development Institute (JNC), PNC TN8410 92130, 1992
|
[2] |
Rebak R B. Selection of corrosion resistant materials for nuclear waste repositories [A]. Materials Science and Technology 2006 [C]. Cincinnati, 2006
|
[3] |
Rebak R B. Materials in nuclear waste disposition [J]. JOM, 2014, 66: 455
|
[4] |
Landolt D, Davenport A, Payer J, et al. A review of materials and corrosion issues regarding canisters for disposal of spent fuel and high-level waste in Opalinus clay [R]. Wettingen: National Cooperative for the Disposal of Radioactive Waste, 2009
|
[5] |
King F. Nuclear waste canister materials: corrosion behavior and long-term performance in geological repository systems [A]. AptedMJ, AhnJ. Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste [M]. 2nd ed. Duxford: Woodhead Publishing, 2017: 365
|
[6] |
Werme L O. Fabrication and testing of Copper canister for long-term isolation of spent nuclear fuel [J]. MRS Online Proc. Library, 1999, 608: 77
|
[7] |
King F, Kolar M. Corrosion of Copper containers prior to saturation of a nuclear fuel waste disposal vault [R]. Pinawa: Atomic Energy of Canada Limited, 1997
|
[8] |
Honda A, Taniguchi N. An assessment of corrosion life of Copper overpack [R]. Tokai: Japan Nuclear Cycle Development Institution, 1999
|
[9] |
Ohba K, Hara N, Sugimoto K, et al. Passivation and depassivation behavior of Carbon Steel in water in contact with bentonite [J]. Zairyo-to-Kankyo, 1996, 45: 209
|
[10] |
King F. Overview of a Carbon Steel container corrosion model for a deep geological repository in sedimentary rock [R]. Toronto: Nuclear Waste Management Organization, 2007
|
[11] |
Martin F, Perrin S, Fenart M, et al. On corrosion of Carbon Steels in Callovo-Oxfordian clay: complementary EIS, gravimetric and structural study providing insights on long term behaviour in French geological disposal conditions [J]. Corros. Eng. Sci. Technol., 2014, 49: 460
|
[12] |
Sumiyama M, Tamata A, Mitsui S, et al. Natural analog research on corrosion behavior of Carbon Steel overpack in bentonite [A]. Proceedings of the 44th Japan Conference on Material and Environment [C]. 1997: 419
|
[13] |
Taniguchi N, Honda A, Ishikawa H. Experimental investigation of passivation behavior and corrosion rate of Carbon Steel in compacted bentonite [J]. MRS Online Proc. Library, 1997, 506: 495
|
[14] |
Wei X, Dong J H, Chen N, et al. Effects of bentonite content on the corrosion evolution of low Carbon Steel in simulated geological disposal environment [J]. J. Mater. Sci. Technol., 2021, 66: 46
doi: 10.1016/j.jmst.2020.04.071
|
[15] |
Taniguchi N, Kawasaki M, Naito M. Corrosion behavior of carbon steel in compacted bentonite saturated with simulated groundwater under anaerobic condition [J]. Zairyo-To-Kankyo, 2010, 59: 418
|
[16] |
Xue F, Liu L Y, Tan L. Aerobic corrosion process of Q235 steel in NaHCO3 solutions [J]. J. Chin. Soc. Corros. Prot., 2022, 42: 771
|
|
薛 芳, 刘两雨, 谭 龙. Q235钢在不同浓度碳酸氢钠溶液中的有氧腐蚀行为 [J]. 中国腐蚀与防护学报, 2022, 42: 771
|
[17] |
Hua F, Pasupathi P, Mon K, et al. Modeling the hydrogen-induced cracking of Titanium Alloys in nuclear waste repository environments [J]. JOM, 2005, 57: 20
|
[18] |
Wei X, Dong J H, Ke W. Crevice corrosion of Grade-2 Ti in simulated groundwater for geological disposal of high-level radioactive nuclear waste [J]. Acta Metall. Sin., 2013, 49: 675
doi: 10.3724/SP.J.1037.2013.00090
|
|
魏 欣, 董俊华, 柯 伟. 工业纯Ti在模拟高放废物地质处置环境中的缝隙腐蚀行为 [J]. 金属学报, 2013, 49: 675
|
[19] |
Ahn T, Jung H, He X, et al. Understanding long-term corrosion of Alloy 22 container in the potential Yucca Mountain repository for high-level nuclear waste disposal [J]. J. Nucl. Mater., 2008, 379: 33
|
[20] |
Rebak R B. Material corrosion issues for nuclear waste disposition in Yucca Mountain [J]. JOM, 2008, 60: 40
|
[21] |
Carranza R M. The crevice corrosion of Alloy 22 in the Yucca Mountain nuclear waste repository [J]. JOM, 2008, 60: 58
|
[22] |
Oda C, Shibata M. Modelling and experimental studies on bentonite-water interaction [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[23] |
Oda C, Shibata M, Yui M. Evaluation of porewater chemistry in the buffer material for the second progress report H12 [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[24] |
Shimodaira S. Corrosion of metals by bacteria [J]. Corros. Eng. Dig., 1973, 22: 2
|
[25] |
Asano E, Sugino H, Kawakami S, et al. Technical development for geological disposal of high-level radioactive waste [R]. Japan: Ishikawajima-Harima Technical Report-4, 1997: 37
|
[26] |
Nishimura T, Wada R, Nishimoto H, et al. The effects of bacteria on the corrosion behavior of Carbon Steel in compacted bentonite [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[27] |
Wang J L, Xu N, Wu T, et al. Response of hydrogen diffusion and hydrogen embrittlement to Cu addition in low carbon low alloy steel [J]. Mater. Charact., 2023, 195: 112478
|
[28] |
Liu Y, Dong F T, Qi C W, et al. Progress of hydrogen embrittlement in pipeline steel [J]. China Metall., 2024, 34(7): 11
|
|
刘 祎, 董福涛, 齐程伟 等. 管线钢氢脆的研究进展 [J]. 中国冶金, 2024, 34(7): 11
|
[29] |
Feng H, Chi Q, Ji L K, et al. Research and development of hydrogen embrittlement of pipeline steel [J]. Corros. Sci. Prot. Technol., 2017, 29: 318
|
|
封 辉, 池 强, 吉玲康 等. 管线钢氢脆研究现状及进展 [J]. 腐蚀科学与防护技术, 2017, 29: 318
|
[30] |
Liu Y, Li Y, Li Q. Effect of cathodic polarization on hydrogen embrittlement susceptibility of X80 pipeline steel in simulated deep sea environment [J]. Acta Metall. Sin., 2013, 49: 1089
doi: 10.3724/SP.J.1037.2013.00271
|
|
刘 玉, 李 焰, 李 强. 阴极极化对X80管线钢在模拟深海条件下氢脆敏感性的影响 [J]. 金属学报, 2013, 49: 1089
|
[31] |
Zhao Y, Wang R. An investigation on mechanical behaviors of pipeline steel X70 after electrochemical hydrogen charging [J]. J. Chin. Soc. Corros. Prot., 2004, 24: 293
|
|
赵 颖, 王 荣. X70管线钢电化学充氢后的力学行为研究 [J]. 中国腐蚀与防护学报, 2004, 24: 293
|
[32] |
Murata T. Role of hydrogen through APC and HE [A]. 78, 79th Nishiyama Commemorative Technical Seminar [C]. Nishiyama: The Iron and Steel Institute of Japan, 1981: 227
|
[33] |
Tanai K, Sato H, Murakami T, et al. A preliminary assessment of gas diffusion and migration [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[34] |
Taniguchi N, Ichikawa S. Measurement of hydrogen content in Carbon Steel exposed to hydrogen gas environment [R]. Japan Nuclear Cycle Development Institute, 1999
|
[35] |
Quick N R, Johnson H H. Hydrogen and deuterium in iron, 49–506 ℃ [J]. Acta Metall., 1978, 26: 903
|
[36] |
Nishimura R, Yamakawa Y, Wataori H. Hydrogen storage of Carbon Steel in carbon dioxide environment [A]. Proceedings of the 44th Japan Conference on Materials and Environments [C]. 1997:429
|
[37] |
Kowaka M. Corrosion damage of metals and corrosion engineering [R]. Kinzoku no Fusyoku Sonsyo to Bosyoku Gijutsu, Agune, 1983
|
[38] |
Oda C, Shibata M. Modelling and experimental studies on benton-ite-water interaction [R]. Japan Nuclear Cycle Development Institution, JNC TN8400-99-032, 1999
|
[39] |
Ikeda A. Research on hydrogen induced cracking of steel in wet hydrogen sulfide environment [D]. Kyoto: Kyoto University, 1981
|
[40] |
Okada H. Stress corrosion cracking and hydrogen cracking of structural steel [A]. Proceeding of 2nd International Conference on SCC and HE of Iron Base Alloys [C]. Firminy: 1977
|
[41] |
Beavers J A, Thompson N G, Parkins R N. Stress-corrosion cracking of low-strength Carbon Steels in candidate high-level waste repository environments [R]. Washington: Nuclear Regulatory Commission, 1987
|
[42] |
Yui M, Sasamoto H, Arthu R C. Groundwater evolution modeling for the second progress performance assessment (PA) report [R]. Japan Nuclear Cycle Development Institute, 1999: 201
|
[43] |
Naito M, Ishihara Y, Umeki H, et al. Study of radiation impact on near field performance of geological disposal system [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[44] |
Honma N, Chiba T, Tanai K. Design concepts for overpack [R]. Japan Nuclear Cycle Development Institute, 1999
|
[45] |
Kasahara K, Sato T. Environmental factors that influence the susceptibility of line pipe steels to external stress corrosion cracking [J]. Tetsu-to-Hagane, 1983, 69: 1463
|
[46] |
Haruna T, Zhu L H, Shibata T. Environment-induced degradation in strength for Carbon Steel in carbonate/bicarbonate solutions containing chloride ions [J]. Zairyo-to-Kankyo, 1998, 47: 771
|
[47] |
Shu R, Shibata T, Haruna T. Initiation condition of SCC in SM400B Carbon Steel in HCO 3 - aqueous solution [A]. Proceedings of 44th Japan Conference on Materials and Environments [C]. 1997: 429
|
[48] |
Kasahara K, Adachi H. Study on material factors that influence the susceptibility of line pipe steels to external stress corrosion cracking [J]. Tetsu-to-Hagane, 1983, 69: 1471
|
[49] |
Taniguchi N, Kawasaki M, Honda A. The critical condition for the initiation of localized corrosion of Carbon Steel in NaCl-NaHCO3-Na2CO3 [C]. Proceedings of 40th Japan Corrosion Conference. 1993: 239
|
[50] |
Honda A, Taniguchi N, Ishikawa H, et al. A modelling study for long-term life prediction of Carbon Steel overpack for geological isolation of high-level redioactive waste [C]. Sapporo: Proceedings of International Symposium on Plant Aging and Life Predictions of Corrodible Structures. 1995: 217
|
[51] |
Taniguchi N, Honda A, Kawasaki M, et al. A study for localization of corrosion on Carbon Steel overpack [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[52] |
Romanoff M. Underground Corrosion [M]. Washington: United States Government Printing Office, 1957
|
[53] |
Marsh G, Bland I, Desport J, et al. Corrosion assessment of metal overpacks for radioactive waste disposal [J]. European Appl. Res. Rept.-Nucl. Sci. Technol. 1983, 5: 223
|
[54] |
Wei X, Liu Y M, Dong J H, et al. Study on corrosion behavior of low Carbon Steel under different water conditions in bentonite of China-Mock-Up [J]. Appl. Clay Sci., 2019, 167: 23
|
[55] |
Xue F, Wei X, Dong J H, et al. Effect of chloride ion on corrosion behavior of low Carbon Steel in 0.1 M NaHCO3 solution with different dissolved oxygen concentrations [J]. J. Mater. Sci. Technol., 2019, 35: 596
|
[56] |
Honda A, Taniguchi N. A corrosion life assessment of overpack for geological isolation of high level radioactive waste [R]. Tokai: Japan Nuclear Cycle Development Institute, 1999
|
[57] |
Wieland E, Wanner H, Albinsson Y, et al. A surface chemical model of the bentonite-water interface and its implications for modelling the near field chemistry in a repository for spent fuel [R]. Stockholm: Swedish Nuclear Fuel and Waste Management, 1994
|
[58] |
Kawasaki M, Honda A. Measurement of effective diffusion coefficient of dissolved oxygen in bentonite [A]. 1994 Autumn Meeting, Atomic Energy Society of Japan, Collection of Drafts K9 [C]. 1994
|
[59] |
Honda A, Taniguchi N, Ishikawa H, et al. Experimental research on corrosion behavior of Carbon Steel in anaerobic condition [J]. PNC Tech. Rev., 1997: 125
|
[60] |
Simpson J, Valloton P. Experiments on container materials for Swiss high-level waste disposal projects Part II [R]. Wettingen: National Cooperative for the Disposal of Radioactive Waste, 1984: 100
|
[61] |
Marsh G P, Bland I D, Taylor K J, et al. An assessment of Carbon Steel overpacks for radioactive waste disposal [R]. Published by the Commission of the European Communities, 1986
|
[62] |
Taniguchi N, Honda A, Kawasaki M, et al. The assessment of corrosion type and corrosion rate of Carbon Steel in compacted bentonite [R]. Japan Nuclear Cycle Development Institute, 1999
|
[63] |
Suzuki S, Fushimi K, Azumi K, et al. AFM observation of micromorphological change of Carbon Steel surface due to corrosion [A]. Proceedings of 44th Japan Conference on Materials and Environments [C]. 1997: 437
|
[64] |
Johnson A B, Francis B. Durability of metals from archaeological objects metal meteorites and native metals [R]. Richland: Battelle Pacific Northwest Laboratories, 1980
|
[65] |
Araki K, Motegi M, Emoto Y, et al. Natural analogue study on engineered barriers for underground disposal of radioactive waste [A]. Proceedings of High Level Radioactive Waste and Spent Fuel Management [C]. Kyoto: 1989: 601
|
[66] |
Kobayashi M, Yokoyama Y, Takahashi R, et al. Long term integrity of overpack closure weld for HLW geological disposal Part 2-corrosion properties under anaerobic conditions [J]. Corros. Eng. Sci. Technol., 2011, 46: 212
|
[67] |
Asano H, Sawa S, Aritomi M. Long-term integrity of waste package final closure for HLW geological disposal, (II). Applicability of TIG welding method to overpack final closure [J]. J. Nucl. Sci. Technol., 2005, 42: 573
|
[68] |
Asano H, Ito T. Long-term integrity of waste package final closure for HLW geological disposal, (V) Applicability of MAG welding method to overpack final closure [J]. J. Nucl. Sci. Technol., 2008, 45: 899
|
[69] |
Asano H, Maeda K, Aritomi M. Long-term integrity of waste package final closure for HLW geological disposal, (III) Applicability of Electron Beam Welding to overpack final closure [J]. J. Nucl. Sci. Technol., 2006, 43: 206
|
[70] |
Taniguchi N, Suzuki H, Kawasaki M, et al. Propagation behaviour of general and localised corrosion of carbon steel in simulated groundwater under aerobic conditions [J]. Energy Mater., 2011, 6: 117
|
[71] |
Liu J Y, Dong L J, Zhang Y, et al. Research progress on sulfide stress corrosion cracking of dissimilar weld joints in oil and gas fields [J]. J. Chin. Soc. Corros. Prot., 2024, 44: 863
|
|
刘久云, 董立谨, 张 言 等. 油气田异种金属焊接接头硫化物应力腐蚀开裂研究进展 [J]. 中国腐蚀与防护学报, 2024, 44: 863
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