journal article·2013-01

Electrochemical and corrosion behavior of a 304 stainless-steel-based metal alloy wasteform in dilute aqueous environments

Jian Chen, R. Matthew Asmussen, Dmitrij Zagidulin, James J. Noël, David W. Shoesmith

Corrosion Science· Volume 66
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Abstract

Abstract The electrochemical and corrosion behavior of a stainless-steel-based alloy made as a prototype metallic nuclear wasteform to immobilize 99Tc, has been studied in a number of reference solutions ranging in pH from 4 to 10. The results showed the 47SS(304)-9Zr–23Mo prototype alloy contained at least five distinct phases with the majority of the Re, used as a Tc surrogate, contained within a Fe2Mo intermetallic phase. Polarization studies showed this alloy exhibited generally passive behavior in a range of dilute aqueous environments. Impedance measurements indicated passivity breakdown events can occur and lead to localized corrosion, especially in slightly alkaline conditions.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals · Fusion materials and technologies

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References (25)

Show source-provided references
1. Yucca Mountain, Nevada – a proposed geologic repository for high-level nuclear waste
2. J.R. Dyer, M.D. Voegel, The Yucca Mountain site characterization project in the United States, Lawrence Berkeley National Laboratory, Report LBNL-49767, 2001.
3. http://www.ne.doe.gov/AFCI/neAFCI.html (August 29, 2012).
4. D. Gombert II, R. Counce, V. Maio, A. Cozzi, J. Marra, J.V. Crum, T. Nenoff, W. Ebert, R. Scheele, C. Jantzen, H. Smith, J. Jerden, B. Spencer, R. Jubin, D. Strachan, M. Kaminski, J. Vienna, Global nuclear energy partnership integrated waste management strategy waste treatment baseline study, vol. I, September 2007, GNEP-WAST-AI-RT-2007-000324.
5. M.J. Williamson, R.L. Sindelar, Development of an Fe-based alloy waste form for spent nuclear fuel, Savannah River National Laboratory, 2009, AFCI-SEPA-WAST-MI-DV-2009-000143/SRNL-STI-2009-00522.
6. Corrosion testing of stainless steel–zirconium metal waste forms10.1557/PROC-556-945 ↗
7. D.D. Keiser, W. Sinkler, D.P. Abraham, J.W. Richardson, S.M. McDeavitt, The effects of actinides on the microstructural development in a metallic high-level nuclear waste form, Argonne National Laboratory, ANL/NT/CP-100293, 1999.
8. D.P. Abraham, S.M. McDeavitt, J. Park, Metal waste forms from the electrometallurgical treatment of spent nuclear fuel, Argonne National Laboratory, ANL/CMT/CP-88008 CONF-9606116-14, 1996.10.2172/238466 ↗
9. N.C. Shroeder, M. Attrep, T. Marrero, Technetium and Iodine Separations in the UREX Process, Los Alamos, NM, 2001, Los Alamos National Laboratory Report: LA-UR-01-6607, 1996.
10. Solvent extraction behavior of minor nuclides in nuclear fuel reprocessing process10.1023/A:1006756215590 ↗
11. The role taken by technetium in the oxidation-reduction processes used in irradiated fuel technology
12. W.L. Ebert, M.A. Lewis, S.G. Johnson, Monitoring the consistency of multiphase waste forms, in: American Nuclear Society, Reno, NV, 2007, 11/11-15/01.
13. W.L. Ebert, Testing to evaluate the suitability of waste forms developed for electrometallurgically treated spent sodium-bonded nuclear fuel for disposal in the Yucca Mountain repository, Argonne National Laboratory, September 2005, ANL-05/43.10.2172/881577 ↗
14. W.L. Ebert, M. Williamson, S. Frank, Immobilizing Tc-bearing waste streams in an iron-based alloy waste form, Argonne, Savannah River, and Idaho National Laboratories, September 2009, AFCI-WAST-PMO-MI-DV-2009- 00160.
15. Evaluation of stainless steel–zirconium alloys as high-level nuclear waste forms10.1016/S0022-3115(98)00433-4 ↗
16. Influence of technetium on the microstructure of a stainless steel–zirconium alloy10.1016/S0022-3115(99)00158-0 ↗
17. Actinide distribution in a stainless steel–15 wt% zirconium high-level nuclear waste form10.1016/S0022-3115(00)00002-7 ↗
18. Microstructural analysis and corrosion behaviour of D9 stainless steel–Zirconium metal waste form alloys10.1016/j.corsci.2010.03.018 ↗
19. Corrosion issues related to disposal of 316 SS-zirconium metal waste form under simulated repository conditions10.1179/1743278210Y.0000000019 ↗
20. Corrosion investigations on metal waste form alloys of titanium-modified Type 316 stainless steel-zirconium in simulated groundwater media10.5006/0525 ↗
21. W.L. Ebert, E. Buck, J. Fortner, Heat treatments of RAW-1 (Re), Argonne and Pacific Northwest National Laboratories, August 2011, FCRD-WAST-2011-000289.
22. Atlas of Eh-pH diagrams: intercomparison of thermodynamic databases, National Institute of Advanced Industrial Science and Technology, Research Center for Deep Geological Environments, Naoto TAKENO, Geological Survey of Japan Open File, Report No. 419, 2005.
23. Analysis of passive films on stainless steel by cyclic voltammetry and Auger spectroscopy10.1149/1.2113959 ↗
24. R. Wada, T. Nishimura, K. Fujiwara, M. Tanabe, M. Mihara, Experimental study on hydrogen gas generation rate from corrosion of Zircaloy and stainless steel under anaerobic alkaline conditions, in: Radioactive Waste Management and Environmental Remediation-ASME American Society for Mechanical Engineering, Fairfield, New Jersey, USA, 1999.
25. Baes · 1976