Self-accelerated corrosion of nuclear waste forms at material interfaces
Abstract
The US plan for high-level nuclear waste includes the immobilization of long-lived radionuclides in glass or ceramic waste forms in stainless-steel canisters for disposal in deep geological repositories. Herein we report that, under simulated repository conditions, corrosion could be significantly accelerated at the interfaces of different barrier materials, which has not been considered in the current safety and performance assessment models. Severe localized corrosion was found at the interfaces between stainless steel and a model nuclear waste glass and between stainless steel and a ceramic waste form. The accelerated corrosion can be attributed to changes of solution chemistry and local acidity/alkalinity within a confined space, which significantly alter the corrosion of both the waste-form materials and the metallic canisters. The corrosion that is accelerated by the interface interaction between dissimilar materials could profoundly impact the service life of the nuclear waste packages, which, therefore, should be carefully thought about when evaluating the performance of waste forms and their packages. Moreover, compatible barriers should be selected to further optimize the performance of the geological repository system.
- Authors:
-
[1];
[4];
[5];
[4];
[4];
[6];
[3];
[1]
- The Ohio State Univ., Columbus, OH (United States)
- Alternative Energies and Atomic Energy Commission (CEA), Bagnols sur Cèze (France)
- Rensselaer Polytechnic Inst., Troy, NY (United States)
- Pennsylvania State Univ., University Park, PA (United States)
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Univ. of North Texas, Denton, TX (United States)
- Publication Date:
- Research Org.:
- Energy Frontier Research Centers (EFRC) (United States). Center for Performance and Design of Nuclear Waste Forms and Containers (WastePD); The Ohio State Univ., Columbus, OH (United States); Rensselaer Polytechnic Inst., Troy, NY (United States); Pennsylvania State Univ., University Park, PA (United States); Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Univ. of North Texas, Denton, TX (United States)
- Sponsoring Org.:
- USDOE Office of Science (SC), Basic Energy Sciences (BES)
- OSTI Identifier:
- 1600995
- Grant/Contract Number:
- SC0016584
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Nature Materials
- Additional Journal Information:
- Journal Volume: 19; Journal Issue: 3; Journal ID: ISSN 1476-1122
- Publisher:
- Springer Nature - Nature Publishing Group
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE
Citation Formats
Guo, Xiaolei, Gin, Stephane, Lei, Penghui, Yao, Tiankai, Liu, Hongshen, Schreiber, Daniel K., Ngo, Dien, Viswanathan, Gopal, Li, Tianshu, Kim, Seong H., Vienna, John D., Ryan, Joseph V., Du, Jincheng, Lian, Jie, and Frankel, Gerald S. Self-accelerated corrosion of nuclear waste forms at material interfaces. United States: N. p., 2020.
Web. doi:10.1038/s41563-019-0579-x.
Guo, Xiaolei, Gin, Stephane, Lei, Penghui, Yao, Tiankai, Liu, Hongshen, Schreiber, Daniel K., Ngo, Dien, Viswanathan, Gopal, Li, Tianshu, Kim, Seong H., Vienna, John D., Ryan, Joseph V., Du, Jincheng, Lian, Jie, & Frankel, Gerald S. Self-accelerated corrosion of nuclear waste forms at material interfaces. United States. https://doi.org/10.1038/s41563-019-0579-x
Guo, Xiaolei, Gin, Stephane, Lei, Penghui, Yao, Tiankai, Liu, Hongshen, Schreiber, Daniel K., Ngo, Dien, Viswanathan, Gopal, Li, Tianshu, Kim, Seong H., Vienna, John D., Ryan, Joseph V., Du, Jincheng, Lian, Jie, and Frankel, Gerald S. Mon .
"Self-accelerated corrosion of nuclear waste forms at material interfaces". United States. https://doi.org/10.1038/s41563-019-0579-x. https://www.osti.gov/servlets/purl/1600995.
@article{osti_1600995,
title = {Self-accelerated corrosion of nuclear waste forms at material interfaces},
author = {Guo, Xiaolei and Gin, Stephane and Lei, Penghui and Yao, Tiankai and Liu, Hongshen and Schreiber, Daniel K. and Ngo, Dien and Viswanathan, Gopal and Li, Tianshu and Kim, Seong H. and Vienna, John D. and Ryan, Joseph V. and Du, Jincheng and Lian, Jie and Frankel, Gerald S.},
abstractNote = {The US plan for high-level nuclear waste includes the immobilization of long-lived radionuclides in glass or ceramic waste forms in stainless-steel canisters for disposal in deep geological repositories. Herein we report that, under simulated repository conditions, corrosion could be significantly accelerated at the interfaces of different barrier materials, which has not been considered in the current safety and performance assessment models. Severe localized corrosion was found at the interfaces between stainless steel and a model nuclear waste glass and between stainless steel and a ceramic waste form. The accelerated corrosion can be attributed to changes of solution chemistry and local acidity/alkalinity within a confined space, which significantly alter the corrosion of both the waste-form materials and the metallic canisters. The corrosion that is accelerated by the interface interaction between dissimilar materials could profoundly impact the service life of the nuclear waste packages, which, therefore, should be carefully thought about when evaluating the performance of waste forms and their packages. Moreover, compatible barriers should be selected to further optimize the performance of the geological repository system.},
doi = {10.1038/s41563-019-0579-x},
journal = {Nature Materials},
number = 3,
volume = 19,
place = {United States},
year = {2020},
month = {1}
}
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Works referenced in this record:
An international initiative on long-term behavior of high-level nuclear waste glass
journal, June 2013
- Gin, S.; Abdelouas, A.; Criscenti, L. J.
- Materials Today, Vol. 16, Issue 6
Colloid Formation During Waste Form Reaction: Implications for Nuclear Waste Disposal
journal, May 1992
- Bates, J. K.; Bradley, J. P.; Teetsov, A.
- Science, Vol. 256, Issue 5057
Pitting Corrosion of Metals
journal, January 1998
- Frankel, G. S.
- Journal of The Electrochemical Society, Vol. 145, Issue 6
Crevice Corrosion of Stainless Steels: I. A Mathematical Model
journal, January 1978
- Oldfield, J. W.; Sutton, W. H.
- British Corrosion Journal, Vol. 13, Issue 1
YUCCA MOUNTAIN: Earth-Science Issues at a Geologic Repository for High-Level Nuclear Waste
journal, May 2004
- Long, Jane C. S.; Ewing, Rodney C.
- Annual Review of Earth and Planetary Sciences, Vol. 32, Issue 1
Aqueous corrosion of borosilicate glass under acidic conditions: A new corrosion mechanism
journal, June 2010
- Geisler, Thorsten; Janssen, Arne; Scheiter, Daniel
- Journal of Non-Crystalline Solids, Vol. 356, Issue 28-30
Effect of Iron on Waste-Glass Leaching
journal, March 1983
- McVAY, Gary L.; Buckwalter, Charles Q.
- Journal of the American Ceramic Society, Vol. 66, Issue 3
Impact of iron on nuclear glass alteration in geological repository conditions: A multiscale approach
journal, April 2013
- Burger, E.; Rebiscoul, D.; Bruguier, F.
- Applied Geochemistry, Vol. 31
Electrochemical Equilibria
book, January 1973
- Pourbaix, Marcel; Staehle, Roger W.; Pourbaix, Marcel
- Lectures on Electrochemical Corrosion, p 83-183
EXAFS Study of Aqueous Zr IV and Th IV Complexes in Alkaline CaCl 2 Solutions: Ca 3 [Zr(OH) 6 ] 4+ and Ca 4 [Th(OH) 8 ] 4+
journal, August 2007
- Brendebach, B.; Altmaier, M.; Rothe, J.
- Inorganic Chemistry, Vol. 46, Issue 16
Aqueous alteration of five-oxide silicate glasses: Experimental approach and Monte Carlo modeling
journal, January 2008
- Arab, M.; Cailleteau, C.; Angeli, F.
- Journal of Non-Crystalline Solids, Vol. 354, Issue 2-9
Contribution of zeolite-seeded experiments to the understanding of resumption of glass alteration
journal, November 2017
- Fournier, Maxime; Gin, Stéphane; Frugier, Pierre
- npj Materials Degradation, Vol. 1, Issue 1
Effect of Zeolite Formation on Borosilicate Glass Dissolution Kinetics
journal, January 2013
- Fournier, Maxime; Frugier, Pierre; Gin, Stéphane
- Procedia Earth and Planetary Science, Vol. 7
Immobilisation of high level nuclear reactor wastes in SYNROC
journal, March 1979
- Ringwood, A. E.; Kesson, S. E.; Ware, N. G.
- Nature, Vol. 278, Issue 5701
Localized Corrosion: Passive Film Breakdown vs. Pit Growth Stability: Part III. A Unifying Set of Principal Parameters and Criteria for Pit Stabilization and Salt Film Formation
journal, January 2018
- Li, Tianshu; Scully, J. R.; Frankel, G. S.
- Journal of The Electrochemical Society, Vol. 165, Issue 11
Modeling glass corrosion with GRAAL
journal, November 2018
- Frugier, Pierre; Minet, Yves; Rajmohan, Natarajan
- npj Materials Degradation, Vol. 2, Issue 1
Archaeological analogs and the future of nuclear waste glass
journal, November 2010
- Verney-Carron, Aurélie; Gin, Stéphane; Libourel, Guy
- Journal of Nuclear Materials, Vol. 406, Issue 3
The Proposed Yucca Mountain Repository from a Corrosion Perspective
journal, January 2006
- Payer, Joe H.
- MRS Proceedings, Vol. 932
The fate of silicon during glass corrosion under alkaline conditions: A mechanistic and kinetic study with the International Simple Glass
journal, February 2015
- Gin, Stéphane; Jollivet, Patrick; Fournier, Maxime
- Geochimica et Cosmochimica Acta, Vol. 151
Evaluation of a simple correction for the hydrocarbon contamination layer in quantitative surface analysis by XPS
journal, July 2005
- Smith, Graham C.
- Journal of Electron Spectroscopy and Related Phenomena, Vol. 148, Issue 1
EXAFS Study of Aqueous ZrIV and ThIV Complexes in Alkaline CaCl2 Solutions: Ca3[Zr(OH)6]4+ and Ca4[Th(OH)8]4+.
journal, October 2007
- Brendebach, B.; Altmaier, M.; Rothe, J.
- ChemInform, Vol. 38, Issue 43
Pitting Corrosion of Metals
journal, January 2010
- Newman, Roger
- The Electrochemical Society Interface, Vol. 19, Issue 1
Pitting Corrosion of Metals [金属の孔食]
journal, January 1967
- Kolotyrkin, Ja. M.
- CORROSION ENGINEERING DIGEST, Vol. 16, Issue 1