High Chrome Refractory Characterization: Part I. Impact of Melt Reduction/Oxidation on the Corrosion Mechanism
Source abstract
Abstract
High Cr 2 O 3 containing Monofrax ™ K‐3 is a robust refractory that is used in the fiberglass industry and used in radioactive waste glass melters worldwide. Monofrax ™ K‐3 is tolerant of transition metal oxides but contains highly reduced solid solutions of spinels, that is, (Mg,Fe 2+ )(Al,Cr) 2 O 3 . Conversely, many of the waste feeds being processed are highly oxidizing. The K‐3 refractory corrosion was tested in sealed crucibles starting with slurried melter feed instead of prereacted glass called for by ASTM C621. Testing the refractory coupon during the feed‐to‐glass conversion exposes the refractory to the oxidizing and reducing species being released during vitrification, for example, NO 3 − , NO 2 − , CO 2 , CO , O 2 . Corrosion rates measured in highly oxidizing (high nitrate) feeds were ~1.8–2.8 times higher than those determined using prereacted glass or reduced feeds. Confirmatory corrosion rates were measured on Monofrax ™ K‐3 coupons immersed in oxidizing feed in a 1/100th‐scale HLW pilot‐scale melter. Corrosion is heterogeneous or incongruent as Ni and Fe in the waste glass exchange with Mg and Al in the refractory. An insoluble NiFe 2 O 4 spinel corrosion product is formed that can build up a protective layer along the refractory walls or spall and settle to the melter floor depending on melt pool convection/agitation.
Source: crossref · Quality: baseline
Research context
OpenAlex topics: Nuclear materials and radiation effects · Concrete and Cement Materials Research · Recycling and utilization of industrial and municipal waste in materials production
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
Savannah River National Laboratory Savannah River Nuclear Solutions Aiken South Carolina 29808
Department of Civil and Environmental Engineering Vanderbilt University Nashville Tennessee 37235
Funding
U.S. Department of Energy
References (48)
Show source-provided references
1. High Chrome Refractory Characterization: Part II. Accumulation of Spinel Corrosion Deposits in Radioactive Waste Glass Melters
2. P. J.CertaandM. N.Wells “River Protection Project System Plan ” ORP‐11242 Rev. 5 DOE Office of River Protection Richland WA November2010.
3. McCauley R. A. · 1996 · 81
4. 10.1179/09506609910152823410.1179/095066099101528234 ↗
5. 10.1111/j.1151-2916.1998.tb02497.x10.1111/j.1151-2916.1998.tb02497.x ↗
6. W. N.Rankin P. E.O'Rourke P. D.Soper M. B.Cosper andB. C.Osgood “Evaluation of Corrosion and Deposition in the 1941 Melter ” U.S. DOE Report DPST‐82‐231 E.I. duPont deNemours & Co. Savannah River Laboratory Aiken SC March 1982.
7. 10.1179/1743280410Y.000000000510.1179/1743280410Y.0000000005 ↗
8. S. A.DegterovandA. D.Pelton “Thermodynamic Calculation of Glass/Slag/Refractory Equilibria in Coal Gasification ”Corrosion of Materials by Molten Glass eds. G.A.Pecoraroet al. Ceram. Trans. V. 78 American Ceramic Society Westerville OH 91–103(1996).
9. 10.1016/0022-3093(86)90779-910.1016/0022-3093(86)90779-9 ↗
10. Miller W. A. · 1975
11. Jantzen C. M. · 1999 · 203
12. D. C.IversonandD. F.Bickford “Evaluation of Materials Performance in a Large‐Scale Glass Melter After Two Years of Vitrifying Simulated SRP Defense Waste ” Sci. Basis for Nucl. Waste Mgt. VIII Mat. Res. Soc. Pittsburgh PA 839–845 1985.10.1557/PROC-44-839 ↗
13. Muan A. · 1965 · 236
14. G. L.Smith D. K.Peeler H. D.Smith P. A.Smith E. M.Tracey andK. D.Wiemers “Effect of Feed Chemistry on Waste Melter Vitrification Kinetics ” U.S. DOE Report PVTD‐T3C‐95‐129 Pacific Northwest Laboratory Richland WA September 1995.
15. 10.1179/09506600010152830410.1179/095066000101528304 ↗
16. Influence of Glass Redox Conditions on the Corrosion of Fusion‐Cast Chrome‐Alumina Refractories
17. Different Types of in situ Refractories
18. G. G.Wicks “Compatibility Tests of Materials for A Prototype Ceramic Melter for Defense Waste Products ” Ceramics in Nuclear Waste Management U.S. DOE Report CONF‐790420 U.S. Dept. of Energy Nat'l. Tech. Info. Service Springfield VA82–85 1979.
19. G. G.Wicks “Corrosion of Melter Materials ” U.S. DOE Report DPST‐79‐580 E.I. duPont deNemours & Co. Savanannah River Laboratory Aiken SC May 1980.
20. Rankin W. N. · 1984 · 559
21. W. N.Rankin “Corrosion of Melter Materials: Part III. Effect of Na2O ” U.S. DOE Report DPST‐81‐933 E.I. duPont deNemours & Co. Savanannah River Laboratory Aiken SC February 1982.
22. Schreiber H. D. · 1996 · 91
23. G. G.Wicks “Melter Materials Compatibility Program Part I: Static and Dynamic Finger Tests‐Simulated Glass Waste ” U.S. DOE Report DPST‐78‐465 E.I. duPont deNemours & Co. Savanannah River Laboratory Aiken SC August 1978.
24. G. G.Wicks “Melter Materials Compatibility Program Part II: Static and Dynamic Finger Tests Radioactive Waste Glass and Long‐Term Simulated Tests ” U.S. DOE Report DPST‐79‐526 E.I. duPont deNemours & Co. Savanannah River Laboratory Aiken SC November 1979.
25. Corning Engineering Laboratory Services Report for W.N. Rankin #11988‐008 July 31 1985.
26. C. M.Jantzenet al. “Melter REDuction/OXidation (REDOX) Control to Optimize Melting and Retain Radionuclides: Part I. High Level Waste Melter REDOX Requirements and Measurement ” (in preparation for IJAGS).
27. 10.1039/an992170091310.1039/an9921700913 ↗
28. 10.1016/S0955-2219(02)00170-X10.1016/S0955-2219(02)00170-X ↗
29. C. M.JantzenandD. P.Lambert “Inspection and Analysis of the Integrated DWPF Melter System (IDMS) After Seven Years of Operation ” U.S. DOE Report WSRC‐RP‐575 Westinghouse Savannah River Co. Aiken SC February 1997.
30. Barin I. · 1989 · 1739
31. A Crucible Study of Spinel Settling in A High‐Level Waste Glass
32. Crucible Study of Spinel Settling in Molten High‐Level Waste Glass
33. J. W.Amoroso D. K.Peeler andT. B.Edwards “Elimination of the Characterization of DWPF Pour Stream Sample and the Glass Fabrication and Testing of the DWPF Sludge Batch Qualification Sample ” U.S. DOE Report SRNL‐STI‐2012‐00157 Rev.0 Savannah River National Laboratory Aiken SC 2012.
34. A. S.Choi “Maximum Total Organic Carbon Limit for DWPF Melter Feed ” U.S. DOE Report WSRC‐TR‐95‐0119 Rev. 0 Westinghouse Savannah River Company Aiken SC March 13 1995.10.2172/403976 ↗
35. 1973
36. Sienko M. J. · 1961 · 623
37. C. M.JantzenandM. E.Stone “Role of Manganese Reduction/Oxidation (REDOX) on Foaming and Melt Rate in High Level Waste (HLW) Melters ” U.S. DOE Report WSRC‐STI‐2006‐00066 Westinghouse Savannah River Co. 2007.10.2172/903096 ↗
38. M. M.Reigel “Literature Review: Assessment of DWPF Melter Lifetime ” U.S. DOE Report SRNL‐STI‐2014‐00134 Savannah River National Laboratory Aiken SC 2014.
39. 10.1533/9780857090959.2.23010.1533/9780857090959.2.230 ↗
40. 10.1111/j.1151-2916.1990.tb06692.x10.1111/j.1151-2916.1990.tb06692.x ↗
41. D. K.PeelerandC. M.Jantzen “Process Control Limits For Poorly Soluble Species In Borosilicate and Soda‐Lime‐Silica Glasses ” U.S. DOE Report (in draft).
42. Volf W. · 1984
43. 10.1111/j.1551-2916.2006.01027.x10.1111/j.1551-2916.2006.01027.x ↗
44. 10.1111/j.1551-2916.2006.01028.x10.1111/j.1551-2916.2006.01028.x ↗
45. S.O BatesandW. M.Bowen “Report on Composition Variation Testing Conducted for Hanford Waste Vitrification ” HWVP‐86‐V1122C Pacific Northwest Laboratory Richland WA 1987.
46. J. M.PerezandR. W.Nakaoka “Vitrification Testing of Simulated High‐Level Radioactive Waste from Hanford ” Waste Management ‘86 R.G. Post (Ed.) Proceedings of the Symposium in Waste Management at Tuscon AZ 495–505 March 2–6 1986.
47. 10.1111/j.1151-2916.1987.tb05712.x10.1111/j.1151-2916.1987.tb05712.x ↗
48. Vitrification of Reactor Wastes