Glass formulation and lab-scale testing of glasses designed for in-can Melter and in-container Vitrification of high-assay low-enriched uranium aqueous polishing Raffinate waste
Source abstract
Abstract
Glasses were designed for processing a nuclear waste from aqueous polishing of high-assay low-enriched uranium using either In-Can Melter or GeoMelt® In-Container Vitrification™ (ICV) technologies, which operate at temperatures of Tp ≤ 1100 °C and Tp ≤ 1450 °C, respectively. Due to the different operating conditions, the melt and glass properties were optimized differently for each technology. Each glass was designed to optimize for maximum waste loading while simultaneously satisfying processing (e.g., crystallization, viscosity, conductivity) and product quality (e.g., durability, hazard characteristic, crystal content) constraints. The raffinate waste contains high nitric acid (4 M) and low total solids (9 g∙L −1) concentrations. Feed preparation processes were tested to facilitate concentration and nitrate destruction/removal while controlling redox of the melter feed. A successful lab-scale feed process including sugar addition and spray-drying was performed to generate an adequate melter feed for ICV processing.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear materials and radiation effects · Glass properties and applications · Recycling and utilization of industrial and municipal waste in materials production
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (69)
Show source-provided references
1. 2022
2. Herczeg · 2019
3. 2021
4. Miller · 2023
5. Vitrification chemistry and nuclear waste10.1016/0022-3093(86)90779-9 ↗
6. Reevaluating the efficacy of moderate annealing in nuclear waste vitrification for sustainable high-level waste management10.1016/j.jclepro.2020.122155 ↗
7. Nuclear waste vitrification in the United States: recent developments and future options10.1111/j.2041-1294.2010.00023.x ↗
8. Ojovan · 2019
9. History of nuclear waste glass in France10.1016/j.mspro.2014.10.002 ↗
10. Glassy wasteforms for nuclear waste immobilization10.1007/s11661-010-0525-7 ↗
11. M.I. Ojovan, O.G. Batyukhnova. 2007. Proc. of Waste Management.
12. Borosilicate glasses for nuclear waste immobilisation
13. The immobilization of high level radioactive wastes using ceramics and glasses10.1023/A:1018646507438 ↗
14. Historical development of glass and ceramic waste forms for high level radioactive wastes
15. Blair · 1976
16. High-level
17. Bjorklund · 1980
18. d'Entremont · 1981
19. Petkus · 1981
20. Didierlaurent · 2019 · 19020
21. Didierlaurent · 2020
22. Formulation and testing of a high-tin borosilicate nuclear waste glass for in-can melting10.1016/j.jnucmat.2023.154643 ↗
23. Kim · 2003
24. Finucane · 2006
25. Witwer · 2008
26. Finucane · 2018
27. Clarke · 2020 · 818
28. Finucane · 2020
29. Garrett · 2020
30. Characterisation and disposability assessment of multi-waste stream in-container vitrified products for higher activity radioactive waste10.1016/j.jhazmat.2020.123764 ↗
31. K. Finucane, K. Witwer, B. Campbell, S. Abeta, M. Yoshioka, J. Reiser, X. Lu, B. Parruzot, J. Vienna. 2023. Proc. Of waste management 2023. Waste Management Symposia.
32. Durability evaluation of glasses to immobilize Fukushima (1F) secondary waste using ASTM C1220 (MCC-1) testing
33. Bray · 1963
34. Smith · 1999
35. Laboratory-scale quartz crucible Melter tests for vitrifying a high-MoO3 Raffinate waste simulant10.1016/j.pnucene.2018.08.022 ↗
36. Darab · 1999 · 556 · 215
37. Oshiro · 2023
38. Gervasio · 2023
39. Vienna · 2016
40. Piepel · 2008
41. Vienna · 2009
42. Hrma · 1994
43. Trier · 1987
44. Mahoney · 2005
45. ASTM C1285-21, standard test methods for determining chemical durability of nuclear, hazardous, and mixed waste glasses and multiphase glass ceramics: the product consistency test (PCT). ASTM C1285-21
46. Characterization of the defense waste processing facility (DWPF) environmental assessment (EA) glass standard reference material (U)
47. 1992
48. 2006
49. Vienna · 2013
50. Non-linear effects of alumina concentration on Product Consistency Test response of waste glasses10.1016/j.jnucmat.2018.09.040 ↗
51. Kim · 2002
52. 2018
53. ASTM C1720-21, standard test methods for determining Liquidus temperature of waste glasses and simulated waste glasses
54. Smith · 1993
55. The liquidus temperature of nuclear waste glasses: an international round-robin study10.1111/j.2041-1294.2011.00063.x ↗
56. ASTM C965-96(2017), Standard practice for measuring viscosity of glass above the softening point
57. DWPF Startup Frit Viscosity Measurement Round Robin Results10.1111/j.1551-2916.2012.05220.x ↗
58. ASTM C657-19, Standard Test Method for D-C Volume Resistivity of Glass. ASTM C657-19
59. Denitration of PUREX Wastes with Sugar
60. Chromium phase behavior in a multi-component borosilicate glass melt10.1016/j.jnoncrysol.2006.02.051 ↗
61. Gervasio · 2021
62. Nepheline crystallization in nuclear waste glasses: progress toward acceptance of high-alumina formulations10.1111/j.2041-1294.2011.00055.x ↗
63. Toward understanding the effect of low-activity waste glass composition on sulfur solubility10.1111/jace.13125 ↗
64. Effect of chlorine and chromium on sulfur solubility in low-activity waste glass10.1111/ijag.16540 ↗
65. Alternative reductants for foam control during vitrification of high-iron high level waste (HLW) feeds10.1016/j.jnoncrysol.2023.122240 ↗
66. Liquidus temperature-composition model for multi-component glasses in the Fe, Cr, Ni, and Mn spinel primary phase field10.1016/S0022-3093(01)00874-2 ↗
67. Vienna · 2002
68. Viscosity of many-component glasses10.1016/j.jnoncrysol.2009.03.005 ↗
69. Reiser · Product consistency test and vapor hydration test comparisons of a radioactive hanford waste glass with its non-radioactive simulant glass. PNNL-34123, Rev. 1 · 202310.2172/1998870 ↗