Research Progress on Corrosion-allowance and High Corrosion-resistant Material Routes for High-level Radioactive Waste Disposal Containers

XIE Jingli; NIU Jiayu; QIAO Shuzhen; WANG Youzhi; HAO Long; CAO Shengfei; WANG Jianqiu

doi:10.19554/j.cnki.1001-3563.2026.19.029

PDF(1311 KB)

Packaging Engineering ›› 2026, Vol. 47 ›› Issue (19) : 287-295. DOI: 10.19554/j.cnki.1001-3563.2026.19.029

Research Progress on Corrosion-allowance and High Corrosion-resistant Material Routes for High-level Radioactive Waste Disposal Containers

XIE Jingli^1,2, NIU Jiayu³, QIAO Shuzhen³, WANG Youzhi³, HAO Long^3,*, CAO Shengfei^1,2, WANG Jianqiu³

Author information +

History +

Abstract

The work aims to review the research progress of these two material routes for different high-level radioactive wastes under different geological disposal concepts, with the focus on comparing their functional roles and applicable environments. Disposal canisters for high-level radioactive wastes are key engineered barriers in multi-barrier disposal systems, and their material route selection is closely linked to the disposal concept. Internationally, two main material routes have been developed: the corrosion-allowance route and the high corrosion-resistant route. The former, typically represented by carbon steel and low-alloy steel, relies on thick-wall design, predictable corrosion behavior, sufficient allowance for wall-thickness loss, and offers the advantages of mature manufacturing, relatively low cost and reliable mechanical properties. The latter, represented by copper and copper-coated composite canisters, emphasizes its intrinsic corrosion resistance and the surface passive-film stability, and usually it forms a composite canister system together with the load-bearing structures to reduce long-term corrosion and failure risks. The results indicate that container material selection should be considered together with host rock type, buffer/backfill materials, groundwater chemistry, redox evolution, and thermo-hydro-mechanical-chemical coupling processes. The corrosion-allowance route depends mainly on predictable corrosion rates and controllable localized corrosion, whereas the high corrosion-resistant route requires careful evaluation of localized corrosion, coating defects, weld integrity, and adaptability to complex environments. Future research in China should shift from comparing individual material properties to evaluating the compatibility between material routes and disposal concepts, and should develop an integrated framework linking materials, engineered barriers, host rocks, and lifetime prediction.

Key words

high-level radioactive waste / geological disposal / disposal container / corrosion-allowance materials / high corrosion-resistant materials

Cite this article

EndNote

Ris (Procite)

Bibtex

Download Citations

XIE Jingli, NIU Jiayu, QIAO Shuzhen, WANG Youzhi, HAO Long, CAO Shengfei, WANG Jianqiu. Research Progress on Corrosion-allowance and High Corrosion-resistant Material Routes for High-level Radioactive Waste Disposal Containers[J]. Packaging Engineering. 2026, 47(19): 287-295 https://doi.org/10.19554/j.cnki.1001-3563.2026.19.029

References

[1] GRAMBOW B.Geological Disposal of Radioactive Waste in Clay[J]. Elements, 2016, 12(4): 239-245.
[2] NAGRA. Project Opalinus Clay: Safety Report: Demonstration of Disposal Feasibility for Spent Fuel, Vitrified High-Level Waste and Long-Lived Intermediate-Level Waste (Entsorgungsnachweis): NTB 02-05[R]. Wettingen: NAGRA, 2002: 1-40.
[3] KING F.Nuclear Waste Canister Materials: Corrosion Behavior and Long-Term Performance in Geological Repository Systems[M]//Geological Repository Systems for Safe Disposal of Spent Nuclear Fuels and Radioactive Waste. 2nd ed. Sawston: Woodhead Publishing, 2017: 365-408.
[4] HEDMAN T, NYSTRÖM A, THEGERSTRÖM C. Swedish Containers for Disposal of Spent Nuclear Fuel and Radioactive Waste[J]. C. R. Phys., 2002, 3(7-8): 903-913.
[5] TANIGUCHI N.Current Status of the Study on the Corrosion of Overpack[C]//Proceedings of the 6th NUCEF Seminar, Tokai: NUCEF, 2003: 25-28.
[6] BEL J J P, WICKHAM S M, GENS R M F. Development of the Supercontainer Design for Deep Geological Disposal of High-Level Heat Emitting Radioactive Waste in Belgium[C]//Proceedings of the 29th International Symposium on the Scientific Basis for Nuclear Waste Management XXIX, Ghent, 2006: 122.1.
[7] 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: NTB 09-02[R]. Wettingen: NAGRA, 2009: 1-73.
[8] CRUSSET D, DEYDIER V, NECIB S, et al.Corrosion of Carbon Steel Components in the French High-Level Waste Programme: Evolution of Disposal Concept and Selection of Materials[J]. Corros. Eng. Sci. Technol., 2017, 52(Sup1): 17-24.
[9] STRÖMBERG B, CALOTA E, LIU J, et al. Assessment of Canister Degradation for the Encapsulation of Spent Nuclear Fuel: Key Research Issues Encountered in Recent Regulatory Reviews and Government Decision Making in Sweden[J]. Adv. Geosci., 2023(62): 31-39.
[10] JOHNSON L H, KING F.Canister Options for the Disposal of Spent Fuel: NTB 02-11[R]. Wettingen: NAGRA, 2003: 1-57.
[11] WANG J.On Area-Specific Underground Research Laboratory for Geological Disposal of High-Level Radioactive Waste in China[J]. J. Rock Mech. Geotech. Eng., 2014, 6(2): 99-104.
[12] WEI X, DONG J, KE W.Progress on a Corrosion Study of Low Carbon Steel for HLW Container in a Simulated Geological Disposal Environment in China[J]. Corros. Commun., 2021(1): 10-17.
[13] TANIGUCHI N, HONDA A, ISHIKAWA H.Experimental Investigation of Passivation Behavior and Corrosion Rate of Carbon Steel in Compacted Bentonite[C]//Proceedings of the 1997 Symposium on Scientific Basis for Nuclear Waste Management XXI, Davos, 1998: 495-501.
[14] SHIBATA T, WATANABE M, TANIGUCHI N, et al.Modelling of Carbon Steel Corrosion under Oxygen Depleted Environment[J]. Corros. Eng. Sci. Technol., 2014, 49(6): 435-441.
[15] KING F, BURT D, GANESHALINGAM J, et al.Coupled Analysis of Mechanical- and Corrosion-Related Degradation of Carbon Steel Spent Fuel Container[J]. Corros. Eng. Sci. Technol., 2014, 49(6): 442-449.
[16] SMART N R, BLACKWOOD D J, WERME L.Anaerobic Corrosion of Carbon Steel and Cast Iron in Artificial Groundwaters: Part 2 - Gas Generation[J]. Corrosion, 2002, 58(8): 627-637.
[17] KWONG G M, WANG S, NEWMAN R C.Performance of a Carbon Steel Container in a Canadian Used Nuclear Fuel Deep Geological Repository[M]//Advances in Materials Science for Environmental and Nuclear Technology II: Ceramic Transactions, Vol. 227. Hoboken: John Wiley & Sons, 2011: 169-182.
[18] KING F.Overview of a Carbon Steel Container Corrosion Model for a Deep Geological Repository in Sedimentary Rock: NWMO TR-2007-01[R]. Toronto: Nuclear Waste Management Organization, 2007: 1-71.
[19] 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]. Corros. Eng. Sci. Technol., 2011, 46(2): 117-123.
[20] REDDY B, PADOVANI C, SMART N R, et al.Further Results on the In Situ Anaerobic Corrosion of Carbon Steel and Copper in Compacted Bentonite Exposed to Natural Opalinus Clay Porewater Containing Native Microbial Populations[J]. Mater. Corros., 2021, 72(1-2): 268-281.
[21] KING F, KOLAR M, KEECH P G.Simulations of Long-Term Anaerobic Corrosion of Carbon Steel Containers in Canadian Deep Geological Repository[J]. Corros. Eng. Sci. Technol., 2014, 49(6): 455-459.
[22] ZHANG Q, ZHENG M, HUANG Y, et al.Long Term Corrosion Estimation of Carbon Steel, Titanium and Its Alloy in Backfill Material of Compacted Bentonite for Nuclear Waste Repository[J]. Sci. Rep., 2019, 9: 3195.
[23] MON K G, BULLARD B E, HUA F, et al.Modeling Alloy 22 General Corrosion in the Yucca Mountain Nuclear Waste Repository[J]. JOM, 2008, 60(1): 52-57.
[24] BRAITHWAITE L J.Galvanic Corrosion of Carbon Steel Coupled to Copper in Used Nuclear Fuel Containers[D]. London: The University of Western Ontario, 2021: 1-148.
[25] STANDISH T E.Galvanic Corrosion of Copper-Coated Carbon Steel for Used Nuclear Fuel Containers[D]. London: The University of Western Ontario, 2019: 23-78.
[26] KOSEC T, QIN Z, CHEN J, et al.Copper Corrosion in Bentonite/Saline Groundwater Solution: Effects of Solution and Bentonite Chemistry[J]. Corros. Sci., 2015, 90: 248-258.
[27] QIAO Y X, WANG T Y, CHEN Z L, et al.Corrosion Techniques and Strategies for Used Fuel Containers with Copper Corrosion Barriers under Deep Geological Disposal Conditions: A Review[J]. Int. J. Miner. Metall. Mater., 2024, 31(12): 2582-2606.
[28] TANIGUCHI N, HONDA A, KAWASAKI M, et al.A Study for Localization of Corrosion on Carbon Steel Overpack: JNC TN8400 99-067[R]. Tokai: Japan Nuclear Cycle Development Institute, 1999: 1-124.
[29] JNC. H12: Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan, Supporting Report 2: Repository Design and Engineering Technology: JNC TN1410 2000-003[R]. Tokai: JNC, 2000: 1-714.
[30] WANG Y Z, QIAO S Z, XIE J L, et al.DRT Analysis on EIS Data to Identify Aerobic-Anaerobic Corrosion Evolution of Low-Carbon Steel under Deep Geological Disposal Condition[J]. Corros. Sci., 2025, 255: 113118.
[31] IDIART A, PĘKALA M. Models for Diffusion in Compacted Bentonite: SKB TR-15-06[R]. Stockholm: Swedish Nuclear Fuel and Waste Management Co. (SKB), 2016: 1-52.
[32] KAUFHOLD S, PLÖTZE M, KLINKENBERG M, et al. Density and Porosity of Bentonites[J]. J. Porous Mater., 2013, 20(1): 191-208.
[33] NECIB S, DIOMIDIS N, KEECH P, et al.Corrosion of Carbon Steel in Clay Environments Relevant to Radioactive Waste Geological Disposals, Mont Terri Rock Laboratory (Switzerland)[M]//BOSSART P, MILNES A G, eds. Mont Terri Rock Laboratory, 20 Years: Two Decades of Research and Experimentation on Claystones for Geological Disposal of Radioactive Waste. Cham: Springer International Publishing, 2018: 331-344.
[34] DILER E, LEBLANC V, GUEUNÉ H, et al.Potential Influence of Microorganisms on the Corrosion of Carbon Steel in the French High-Level Long-Lived Nuclear Waste Disposal Context at 50 °C[J]. Mater. Corros., 2023, 74(11-12): 1777-1794.
[35] KURSTEN B, GAGGIANO R, CAES S, et al.History of Corrosion Studies on Container Materials for the Final Disposal of VHLW and SF Conducted in Belgium[J]. Mater. Corros., 2023, 74(11-12): 1587-1618.
[36] KURSTEN B, SMART N R, SENIOR N A, et al.Overview of Anaerobic Corrosion of Carbon Steel Radioactive Waste Packages in Alkaline Media in Support of the Belgian Supercontainer Concept[J]. Mater. Corros., 2021, 72(1-2): 32-51.
[37] GAGGIANO R.The Anaerobic Corrosion of the Carbon Steel Overpack under Anoxic Alkaline Conditions Representing the Belgian Supercontainer Concept[C]//Proceedings of the Interdisciplinary Research Symposium on the Safety of Nuclear Disposal Practices (safeND 2023), Berlin, 2023: 41-41.
[38] SMART N R, RANCE A P, FENNELL P A H, et al. The Anaerobic Corrosion of Carbon Steel in Alkaline Media - Phase 2 Results[C]//Proceedings of the 3rd International Workshop on Long-Term Performance of Cementitious Barriers and Reinforced Concrete in Nuclear Power Plant and Radioactive Waste Storage and Disposal (NUCPERF 2012), Cadarache, 2013: 06003.
[39] KOVALOV D, GHANBARI E, MAO F, et al.Investigation of Artificial Pit Growth in Carbon Steel in Highly Alkaline Solutions Containing 0.5 M NaCl under Oxic and Anoxic Conditions[J]. Electrochim. Acta, 2019, 320: 134554.
[40] SMART N R, RANCE A P, FENNELL P A H, et al. Effect of Sulphur Species on Anaerobic Corrosion of Carbon Steel in Alkaline Media[J]. Corros. Eng. Sci. Technol., 2014, 49(6): 473-479.
[41] U.S.DEPARTMENT OF ENERGY. Viability Assessment of a Repository at Yucca Mountain. Volume 3: Total System Performance Assessment: DOE/RW-0508/V3[R]. North Las Vegas: U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Yucca Mountain Site Characterization Office, 1998: 1-523.
[42] KING F.Container Materials for the Storage and Disposal of Nuclear Waste[J]. Corrosion, 2013, 69(10): 986-1011.
[43] SMAILOS E, SCHWARZKOPF W, KIENZLER B, et al.Corrosion of Carbon-Steel Containers for Heat-Generating Nuclear Waste in Brine Environments Relevant for a Rock-Salt Repository[C]//Scientific Basis for Nuclear Waste Management XV: Proceedings of the 15th International Symposium on the Scientific Basis for Nuclear Waste Management, Strasbourg, 1992: 399-406.
[44] SMAILOS E.Influence of Welding and Heat Treatment on Corrosion of a High-Level Waste Container Material Carbon Steel in Disposal Salt Brines[J]. Corrosion, 2000, 56(10): 1071-1074.
[45] SMAILOS E, KIENZLER B.Galvanic Corrosion between the Nuclear Waste Disposal Container Material Pairs of Copper-Nickel Alloys and Carbon Steel in Salt Brines[J]. Corrosion, 2005, 61(3): 230-236.
[46] WERSIN P, HADI J, JENNI A, et al.Interaction of Corroding Iron with Eight Bentonites in the Alternative Buffer Materials Field Experiment (ABM2)[J]. Minerals, 2021, 11(8): 907.
[47] JOHNSON L H, NIEMEYER M, KLUBERTANZ G, et al.Calculations of the Temperature Evolution of a Repository for Spent Fuel, Vitrified High-Level Waste and Intermediate Level Waste in Opalinus Clay: NTB 01-04[R]. Wettingen: NAGRA, 2002: 1-80.
[48] SMART N R, BLACKWOOD D J, WERME L.Anaerobic Corrosion of Carbon Steel and Cast Iron in Artificial Groundwaters: Part 1 - Electrochemical Aspects[J]. Corrosion, 2002, 58(7): 547-559.
[49] SUN Y P, WEI X, DONG J H, et al.Understanding the Role of Alloyed Ni and Cu on Improving Corrosion Resistance of Low Alloy Steel in the Simulated Beishan Groundwater[J]. J. Mater. Sci. Technol., 2022, 130: 124-135.