Microstructural analysis and corrosion behavior of zirconium-stainless steel metallic waste form
Source abstract
Abstract
Abstract Management of radioactive metallic waste using “alloy melting route” is currently being investigated by several researchers. In the present study, potentiodynamic polarizations were conducted on six as-cast zirconium (Zr)-stainless steel (SS) alloys (i.e. Zr-25, 20, 16, 12, 8 and 5 wt.% SS) at pH = 1, 5 and 8. Electrochemical behavior of metallic-waste-form (MWF) alloys containing more than 16 wt.% SS showed lower potentials at the break down of passivity attributed to localized attack mainly at Cr-depleted matrix–intermetallic interfaces. Zr–5SS and Zr–12SS alloys contain Zr3(Fe, Cr, Ni)/Zr3(Fe, Cr)-type of phases and their interfaces with matrices were prone to localized attack. Whereas, Zr–8SS and Zr–16SS alloys demonstrated better corrosion resistance in comparison to Zr–5SS and Zr–12SS respectively. In addition, occurrence of Laves phase, e.g. Zr2(Fe, Cr), in Zr–8SS and Zr–16SS alloys makes them suitable for MWF.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear materials and radiation effects · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (51)
Show source-provided references
1. Materials Issues in Nuclear-Waste Management10.1007/s11837-000-0183-0 ↗
2. Radioactive Waste Management10.13182/NT91-A34525 ↗
3. Cementitious Materials for Nuclear Waste Immobilization
4. Corrosion issues in the French high-level nuclear waste program10.5006/1.3319129 ↗
5. Abraham · 2000
6. Studies on immobilization of thorium in barium borosilicate glass10.1016/j.jnucmat.2006.09.012 ↗
7. Barium borosilicate glass - a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste10.1016/j.jnucmat.2006.07.004 ↗
8. Corrosion of Alloy 690 process pot by sulfate containing high level radioactive waste at feed stage10.1016/j.jnucmat.2007.08.005 ↗
9. International Atomic Energy Agency · 1985 · 1
10. Ojovan · 2005
11. Preliminary study on calcium aluminosilicate glass as a potential host matrix for radioactive 90Sr-An approach based on natural analogue study10.1016/j.jhazmat.2011.03.031 ↗
12. Role of sulfate in structural modifications of sodium barium borosilicate glasses developed for nuclear waste immobilization10.1111/j.1551-2916.2008.02773.x ↗
13. Earth Planet. Plutonium and 'minor' actinides: safe sequestration
14. Viscosity of many-component glasses10.1016/j.jnoncrysol.2009.03.005 ↗
15. Glass - an environmental protector
16. Thermodynamic Approach to Glass Corrosion
17. Summary and Evaluation of Waste Forms
18. The immobilization of high level radioactive wastes using ceramics and glasses10.1023/A:1018646507438 ↗
19. Bauer · 2000
20. Preparation and Processing of the Metallic Waste Form
21. International Atomic Energy Agency · 1985 · 1
22. Jardine · 1994
23. Microstructure and phase identification in type 304 stainless steel-zirconium alloys10.1007/BF02651870 ↗
24. Treatment of wastes in the ifr fuel cycle10.1016/0149-1970(96)00008-X ↗
25. Abraham · 1996
26. McDeavitt · 1994 · 305
27. Evaluation of stainless steel– zirconium alloys as high-level nuclear waste forms10.1016/S0022-3115(98)00433-4 ↗
28. Microstructural analysis and corrosion behaviour of D9 stainless steel–Zirconium metal waste form alloys10.1016/j.corsci.2010.03.018 ↗
29. Corrosion issues related to disposal of 316 SS-zirconium metal waste form under simulated repository conditions10.1179/1743278210Y.0000000019 ↗
30. Corrosion investigations on metal waste form alloys of titanium-modified Type 316 stainless steel-zirconium in simulated groundwater media10.5006/0525 ↗
31. Metallurgical characterizations of Fe–Cr–Ni–Zr base alloys developed for geological disposal of radioactive hulls10.1016/j.jnucmat.2011.11.008 ↗
32. Electrochemical and corrosion behavior of a 304 stainless-steel-based metal alloy wasteform in dilute aqueous environments10.1016/j.corsci.2012.09.012 ↗
33. D. P. Abraham, Lin J. Simpson, M.J. Devries, S.M. Mcdeavitt, Corrosion testing of stainless steel-zirconium metal waste forms, Mater. Res. Soc. Symp. Proc. 556, pp. 945–952.10.1557/PROC-556-945 ↗
34. Laves intermetallics in stainless steel-zirconium alloys10.1016/S0921-5093(97)00649-7 ↗
35. The lattice parameters and solubility limits of alpha iron as affected by some binary transition-element additions
36. Host phases for actinides in simulated metallic waste forms10.1016/j.jnucmat.2003.08.032 ↗
37. Sedriks · 1979
38. Formation of Oxides on Some Stainless Steels at High Temperatures
39. Passive film of 18-8 stainless steel structure and its function10.1016/0010-938X(73)90031-0 ↗
40. Phase transformation at Ta/Zr bonded interface - study on bonding of zirconium and stainless steel10.2207/qjjws.17.59 ↗
41. Influence of σ-phase on mechanical properties and corrosion resistance of duplex stainless steels10.1016/S0010-938X(99)00009-8 ↗
42. Effects of solution treatment and continuous cooling on σ-phase precipitation in a 2205 duplex stainless steel10.1016/S0921-5093(01)00911-X ↗
43. Influence of sigma-phase formation on the localized corrosion behavior of a duplex stainless steel10.1007/BF02648847 ↗
44. Effects of sigma phase on the initiation and propagation of pitting corrosion of duplex stainless steel10.5006/1.3278163 ↗
45. Correlation between critical pitting temperature and degree of sensitisation on alloy 2205 duplex stainless steel10.1016/j.corsci.2010.10.009 ↗
46. Evaluation of aged duplex stainless steel UNS S32750 susceptibility to intergranular corrosion by optimized double loop electrochemical potentio-kinetic reactivation method10.1016/j.corsci.2012.11.024 ↗
47. Callister · 2007
48. Anodic Polarization Behavior Of Nickel-Chromium Alloys In Sulfuric Acid Solution10.5006/0010-9312-21.9.277 ↗
49. Irradiation-enhanced second-phase precipitation in Zr-Fe nanocrystalline thin films
50. Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel10.1007/BF02914763 ↗
51. Influence of technetium on the microstructure of a stainless steel-zirconium alloy10.1016/S0022-3115(99)00158-0 ↗