journal article·2021-12-20Open access

Forty years of durability assessment of nuclear waste glass by standard methods

Clare L. Thorpe, James J. Neeway, Carolyn I. Pearce, Russell J. Hand, Adam J. Fisher, Sam A. Walling, Neil C. Hyatt, Albert A. Kruger, Michael Schweiger, David S. Kosson, Christina L. Arendt, Jose Marcial, Claire L. Corkhill

npj Materials Degradation· Volume 5· Issue 1

Abstract

Abstract Standard methods to assess the durability of vitrified radioactive waste were first developed in the 1980’s and, over the last 40 years, have evolved to yield a range of responses depending on experimental conditions and glass composition. Mechanistic understanding of glass dissolution has progressed in parallel, enhancing our interpretation of the data acquired. With the implementation of subsurface disposal for vitrified radioactive waste drawing closer, it is timely to review the available standard methodologies and reflect upon their relative advantages, limitations, and how the data obtained can be interpreted to support the post-closure safety case for radioactive waste disposal.
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Research context

OpenAlex topics: Nuclear materials and radiation effects · Radioactive element chemistry and processing · Concrete and Cement Materials Research

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References (100+)

Show source-provided references
1. Jantzen, C. M. Historical development of glass and ceramic waste forms for high level radioactive wastes. In Handbook of Advanced Radioactive Waste Conditioning Technologies. (ed Ojovan, M. I.) Ch. 6, 159–172 (Woodhead, 2011).10.1533/9780857090959.1.159 ↗
2. Jantzen, C. M. Development of glass matrices for high level radioactive wastes. In Handbook of Advanced Radioactive Waste Conditioning Technologies (ed Ojovan, M. I.). Ch. 9, 230–292 (Woodhead, 2011).10.1533/9780857090959.2.230 ↗
3. Jantzen, C. M., Lee, W. E. & Ojovan, M. I. Radioactive waste (RAW) conditioning, immobilisation, and encapsulation processes and technologies: overview and advances. In Radioactive Waste Management and Contaminated Site Clean-up: Processes, Technologies and International Experience (eds Lee, W. E., Ojovan, M. I. & Jantzen, C. M.). Ch. 6, 171–272 (Woodhead, 2013).10.1533/9780857097446.1.171 ↗
4. Kim, C. W., Park, J. K. & Hwang, T. W. Analysis of leaching behavior of simulated LILW glasses by using the MCC-1 test method. J. Nucl. Sci. Technol. 48, 1108–1114 (2011).10.1080/18811248.2011.9711796 ↗
5. Pierce, E. M. et al. Integrated Disposal Facility FY2010 Glass Testing Summary Report. PNNL - 19736. U.S. Department of Energy. https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-19736.pdf (2020).10.2172/1004828 ↗
6. Bingham, P. A., Connelly, A. J., Hand, R. J. & Hyatt, N. C. Vitrification of UK intermediate level radioactive wastes arising from site decommissioning: property modelling and selection of candidate host glass compositions. Glass Technol.: Eur. J. Glass Sci. Technol. Part A 53, 83–100 (2012).
7. THERAMIN, 2019, Thermal treatment for radioactive waste minimization and hazard reduction. http://www.theramin-h2020.eu/ (2021).
8. PREDIS (Pre-disposal management of radioactive waste). https://predis-h2020.eu/predis-project/ (2020).
9. Walling, S. A. et al. Characterisation and disposability assessment of multi-waste stream in-container vitrified products for higher activity radioactive waste. J. Hazard. Mater. 401, 123764 (2021).10.1016/j.jhazmat.2020.123764 ↗
10. Hyatt, N. C. & James, M. Thermal treatment of ILW. Nucl. Eng. Inter. 58, 10–13 (2013).
11. Hyatt, N. C. et al. Thermal treatment of simulant plutonium contaminated materials from the Sellafield site by vitrification in a blast-furnace slag. J. Nucl. Mater. 444, 186–199 (2014).10.1016/j.jnucmat.2013.08.019 ↗
12. Tan, S., Kirk, N., Marshall, M., McGann, O. & Hand, R. J. Vitrification of an intermediate level Magnox sludge waste. J. Nucl. Mater. 515, 392–400 (2019).10.1016/j.jnucmat.2019.01.007 ↗
13. Harnett, L. C., Gardner, L. J., Sun, S., Mann, C. & Hyatt, N. C. Reactive spark plasma sintering of Cs-exchanged chabazite: characterisation and durability assessment for Fukushima Daiichi NPP clean-up. J. Nucl. Sci. Technol. 56, 891–901 (2019).10.1080/00223131.2019.1602484 ↗
14. McGrail, B. P., Bacon, D. H., Serne, R. J. & Pierce, E. M. A Strategy to Assess Performance of Selected Low-activity Waste Forms in An Integrated Disposal Facility. PNNL-14362 (Pacific Northwest National Laboratory, 2003).10.2172/15010301 ↗
15. Goel, A., McCloy, J. S., Pokorny, R. & Kruger, A. A. Challenges with vitrification of Hanford high-level waste (HLW) to borosilicate glass—an overview. J. Non-Cryst. Solids .: X 4, 100033 (2019).
16. Kim, C. & Day, D. E. Immobilization of Hanford LAW in iron phosphate glasses. J. Non-Cryst. Solids 331, 20–31 (2003).10.1016/j.jnoncrysol.2003.08.070 ↗
17. Brow, R. K., Kim, C. W. & Reis, S. T. Iron polyphosphate glasses for waste immobilization. Int. J. Appl. Glass Sci. 11, 4–14 (2020).10.1111/ijag.13565 ↗
18. IAEA. Geological Disposal Facilities for Radioactive Waste. IAEA Safety Standard Series, No. SSG-14. https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1483_web.pdf (2011).
19. IAEA. Scientific and Technical Basis for the Geological Disposal of Radioactive Wastes. Technical report series, No. 413, (IAEA, 2003).
20. IAEA. Performance of Engineered Barrier Materials in Near Surface Disposal Facilities for Radioactive Waste (IAEA, 2001).
21. Corkhill, C. L. & Hyatt, N. C. Nuclear Waste Management. Physics World Discovery (IOP Publishing, 2018).10.1088/978-0-7503-1638-5 ↗
22. Harrison, M. T. Review of glass dissolution rates for use in the disposal system safety case performance assessment models. NNL 10, 10734 (2010).
23. Kim, M. et al. Leaching behaviors and mechanisms of vitrified forms for the low-level radioactive solid wastes. J. Hazard. Mater. 384, 121296 (2020).10.1016/j.jhazmat.2019.121296 ↗
24. National Research Council. Waste Forms Technology and Performance: Final Report (The National Academies Press, 2011).
25. Strachan, D. M. Glass dissoltion: testing and modeling for long-term behaviour. J. Nucl. Mater. 298, 69–77 (2001).10.1016/S0022-3115(01)00572-4 ↗
26. Inagaki, Y. Microchannel as a tool to investigate glass dissolution kinetics. Proc. Mat. Sci. 7, 172–178 (2014).
27. Fournier, M. et al. Glass dissolution rate measurement and calculation revisited. J. Nucl. Mat. 476, 140–154 (2016).10.1016/j.jnucmat.2016.04.028 ↗
28. Varshneya, A. K. & Mauro, J. C. Fundamentals of Inorganic Glasses, third edn. (Elsevier, 2019).10.1016/B978-0-12-816225-5.00022-5 ↗
29. Ojovan, M. I., Lee, W. E. & Kalmykov, S. N. (eds). Performance of wasteform materials. In An Introduction to Nuclear Waste Immobilisation, third edn. Ch. 23, 433–461 (Elsevier, 2019).10.1016/B978-0-08-102702-8.00023-6 ↗
30. Strachan, D. Glass dissolution as a function of pH and its implications for understanding mechanisms and future experiments. Geochim. Cosmochim. Acta 219, 111–123 (2017).10.1016/j.gca.2017.09.008 ↗
31. Gin, S., Frugier, P., Jollivet, P. & Bruguier, F. New insight into the residual rate of borosilicate glasses: effect of S/V and glass composition. Int. J. Appl. Glass Sci. 4, 371–382 (2013).10.1111/ijag.12048 ↗
32. Frugier, P. et al. SON68 nuclear glass dissolution kinetics: current state of knowledge and basis of the new GRAAL model. J. Nucl. Mater. 380, 8–21 (2008).10.1016/j.jnucmat.2008.06.044 ↗
33. Gin, S. et al. Origin and consequences of silicate glass passivation by surface layers. Nat. Commun. 6, 8 (2015).
34. Bunker, B. C. Molecular mechanisms for corrosion of silica and silicate glasses. J. Non-Cryst. Solids 179, 300–308 (1994).10.1016/0022-3093(94)90708-0 ↗
35. Grambow, B. A general rate equation for nuclear waste glass corrosion, in Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C., Stone, J. and Ewing, R. Mat. Res. Soc. Proc. 44, 15–24 (1984).10.1557/PROC-44-15 ↗
36. Van Iseghem, P. et al. Glamor- or how we achieved a common understanding on the decrease of glass dissolution kinetics through international cooperation. J. South Carol. Acad. Sci. 9, 6 (2011).
37. Fournier, M., Gin, S. & Frugier, P. Resumption of nuclear glass alteration: state of the art. J. Nucl. Mater. 448, 348–363 (2014).10.1016/j.jnucmat.2014.02.022 ↗
38. Gin, S. Insights into the mechanisms controlling the residual corrosion rate of borosilicate glasses. npj Mater. Degrad. 4, 41 (2020).
39. Ojovan, M. I., Pankov, A. S. & Lee, W. E. The ion exchange phase in corrosion of nuclear waste glasses. J. Nucl. Mater. 358, 57–68 (2006).10.1016/j.jnucmat.2006.06.016 ↗
40. Gin, S. Atom-probe tomography, TEM and ToF-SIMS study of borosilicate glass alteration rim: a multiscale approach to investigating rate-limiting mechanisms. Geochim. Cosmochim. Acta, 202, 57–76 (2017).10.1016/j.gca.2016.12.029 ↗
41. Geisler, T. et al. The mechanism of borosilicate glass corrosion revisited. Geochim. Cosmochim. Acta 158, 112–129 (2015).10.1016/j.gca.2015.02.039 ↗
42. Geisler, T. et al. Aqueous corrosion of borosilicate glass under acidic conditions: a new corrosion mechanism. J. Non-Cryst. Solids 356, 1458–1465 (2010).10.1016/j.jnoncrysol.2010.04.033 ↗
43. Van Iseghem, P. & Grambow, B. The long-term corrosion and modelling of two simulated Belgian reference high-level waste glasses. In Scientific Basis for Nuclear Waste. (eds Apted, M. J. & Westerman, R. E.) p. 631 (MRS Proceedings, Cambridge University Press, 1988). https://doi.org/10.1557/PROC-112-631.10.1557/PROC-112-631 ↗
44. Strachan, D. M. & Croak, T. L. Compositional effects on long-term dissolution of borosilicate glass. J. Non-Crystalline Solids 272, 22–33 (2000).10.1016/S0022-3093(00)00154-X ↗
45. Strachan, D. M. & Neeway, J. J. Effects of alteration product precipitation on glass dissolution. Appl. Geochem. 45, 144–157 (2014).10.1016/j.apgeochem.2014.03.013 ↗
46. Fournier, M. et al. Effect of pH on the stability of passivating gel layers formed on International Simple Glass. J. Nucl. Mater. 524, 21–38 (2019).10.1016/j.jnucmat.2019.06.029 ↗
47. Mercado-Depierre, S., Fournier, M., Gin, S. & Angeli, F. Influence of zeolite precipitation on borosilicate glass alteration under hyperalkaline conditions. J. Nucl. Mater. 491, 67–82 (2017).10.1016/j.jnucmat.2017.04.043 ↗
48. Ojovan, M. On alteration rate renewal stage of nuclear waste glass corrosion. MRS Adv. 5, 111–120 (2020).10.1557/adv.2020.36 ↗
49. Majérus, O. et al. Glass alteration in atmospheric conditions: crossing perspectives from cultural heritage, glass industry, and nuclear waste management. npj Mater. Degrad. 4, 27 (2020).10.1038/s41529-020-00130-9 ↗
50. Alternative Waste Form Peer Review Panel. The Evaluation and Review of Alternative Waste Forms for Immobilization of High-level Radioactive Wastes. Report number 2, DOE/TIC-11219 (United States Department of Energy, 1980).
51. Bernadzikowski, T. A. The Evaluation and Selection of Candidate High Level Waste Forms. USDOE/TIC-11611 (National Technical Info. Service, 1982).10.2172/5197476 ↗
52. Interface Working Group on High-Level Waste Form Selection Factors. A Method for Product Performance Evaluation of Candidate Waste Forms for Immobilization of High-level Radioactive Wastes. DOG/TIC-1 1612 (United States Department of Energy, 1982).
53. Hespe, E. D. Leach testing of immobilized radioactive waste solids. Atomic Energy Rev. 9, 195–207 (1971).
54. MCC, Material Characterization Center. Nuclear Waste Materials Handbook. DOE/TIC 11400 (Pacific Northwest National Laboratory, 1981).
55. Abdelouas, A. et al. A preliminary investigation of the ISG glass vapour hydration. Int. J. Appl. Glass Sci. 4, 207–316 (2013).10.1111/ijag.12055 ↗
56. Chinnam, R. K., Fossati, P. C. M. & Lee, W. E. Degradation of partially immersed glass: a new perspective. J. Nucl. Mater. 503, 56–65 (2018).10.1016/j.jnucmat.2018.02.040 ↗
57. McGrail, B. P., Ebert, W. L., Bakel, A. L. & Peeler, D. K. Measurement of kinetic rate law parameters on a Na.Ca.Al borosilicate glass for low-activity waste. J. Nucl. Mater. 249, 175–189 (1997).10.1016/S0022-3115(97)00213-4 ↗
58. Inagaki, Y. et al. Initial dissolution rate of a Japanese simulated high-level waste glass P0798 as a function of pH and temperature measured by using micro-channel flow-through test method. J. Nucl. Sci. Technol. 49, 438–449 (2012).10.1080/00223131.2012.669246 ↗
59. Neeway, J. J., Rieke, P. C., Parruzot, B. P., Ryan, J. V. & Asmussen, R. M. The dissolution behavior of borosilicate glasses in far-from equilibrium conditions. Geochim. Cosmochim. Acta 226, 132–148 (2018).10.1016/j.gca.2018.02.001 ↗
60. Vienna, J. D., Neeway, J. J., Ryan, J. V. & Kerisit, S. N. Impacts of glass composition, pH, and temperature on glass forward dissolution rate. npj Mater. Degrad. 2, 22 (2018).10.1038/s41529-018-0042-5 ↗
61. Inagaki, Y., Kikunaga, T., Idemitsu, K. & Arima, T. Initial dissolution rate of the International Simple Glass as a function of pH and temperature measured by using micro-channel flow-through test method. Int. J. Appl. Glass Sci. 4, 317–327 (2013).10.1111/ijag.12043 ↗
62. Icenhower, J. & Dove, P. M. The dissolution kinetics of amorphous silica into sodium chloride solutions: effects of temperature and ionic strength. Geochim. Cosmochim. Acta 64, 4193–4203 (2000).10.1016/S0016-7037(00)00487-7 ↗
63. Wolff-Boenisch, D., Gislason, S. R., Oelkers, E. H. & Putnis, C. V. The dissolution rates of natural glasses as a function of their composition at pH 4 and 10.6, and temperatures from 25 to 74 °C. Geochim. Cosmochim. Acta 68, 4843–4858 (2004).10.1016/j.gca.2004.05.027 ↗
64. Criscenti, L. J., Kubicki, J. D. & Brantley, S. L. Silicate glass and mineral dissolution: calculated reaction paths and activation energies for hydrolysis of a Q3 Si by H3O+ using ab initio methods. J. Phys. Chem. A. 110, 198–206 (2006).10.1021/jp044360a ↗
65. McGrail, B. P. & Olson, K. M. Evaluating Long-term Performance of In-situ Vitrified Waste Forms: Methodology and Results. PNL-8358 (Pacific Northwest National Laboratory, 1992).10.2172/6745039 ↗
66. McGrail, B. P. & Peeler, D. K. Evaluation of the Single-pass Flow-through Test to Support a Low-activity Waste Specification. PNL-10746 (Pacific Northwest National Laboratory, 1995).10.2172/106527 ↗
67. ASTM C1662, Standard Practice for Measurement of the Glass Dissolution Rate Using the Single-Pass Flow-Through Test Method, ASTM C1662 (2018).
68. Caes, S., Ferrand, K. & Lemmens, K. Topical report on dynamic dissolution test on SON68, SM513, SM539 and ISG glasses. Sck.cen Report. SCK CEN/37731394, Revision 1. https://publications.sckcen.be/portal/files/6978728/ResearchOutput-37731394.pdf (2020).
69. Cassingham, N. et al. The initial dissolution rates of simulated UK Magnox-ThORP blend nuclear waste glass as a function of pH, temperature and waste loading. Mineral. Mag. 79, 1529–1542 (2015).10.1180/minmag.2015.079.6.28 ↗
70. Corkhill, C. L., Fisher, A. J., Strachan, D. M., Hand, R. J. & Hyatt, N. C. Corrigendum to ‘The initial dissolution rates of simulated UK Magnox-ThORP blend nuclear waste glass as a function of pH, temperature and waste loading’ (Mineralogy Mag. 79, 1529–1542 (2015)). Mineral. Mag. 82, 939–942 (2018).10.1180/minmag.2017.081.077 ↗
71. Backhouse, D. J. et al. Corrosion of the International Simple Glass under acidic to hyperalkaline conditions. npj Mater. Degrad. 2, 29 (2018).10.1038/s41529-018-0050-5 ↗
72. Iwalewa, T. M., Qu, T. & Farnan, I. Investigation of the maximum dissolution rates and temperature dependence of a simulated UK nuclear waste glass in circum-neutral media at 40 and 90 °C in a dynamic system. Appl. Geochem. 82, 177–190 (2017).10.1016/j.apgeochem.2017.05.018 ↗
73. Hellmann, R. et al. Nanometer-scale evidence for interfacial dissolution-reprecipitation control of silicate glass corrosion. Nat. Mater. 14, 307–311 (2015).10.1038/nmat4172 ↗
74. Geisler, T., Dohmen, L., Lenting, C. & Fritzsche, M. B. K. Real-time in situ observations of reaction and transport phenomena during silicate glass corrosion by fluid-cell Raman spectroscopy. Nat. Mater. 18, 342–348 (2019).10.1038/s41563-019-0293-8 ↗
75. Fisher, A. J., Hyatt, N. C., Hand, R. J. & Corkhill, C. L. The formation of pitted features on the International Simple Glass during dynamic experiments at alkaline pH. MRS Adv. 4, 993–999 (2019).10.1557/adv.2019.9 ↗
76. Delage, F. & Dussossoy, J. L. R7T7 glass initial dissolution rate measurements using a high-temperature soxhlet device. MRS Online Proc. Libr. 212, 41–47 (1990).10.1557/PROC-212-41 ↗
77. Crum, J. V. et al. Dilute condition corrosion behavior of glass-ceramic waste form. J. Nucl. Mater. 482, 1–11 (2016).10.1016/j.jnucmat.2016.08.002 ↗
78. ASTM C1285. Standard Test Methods for Determining the Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT). ASTM C1285-21 (ASTM, 2014).
79. Ebert, W. L. & Wolf, S. F. An interlaboratory study of a standard glass for acceptance testing of low-activity waste glass. J. Nucl. Mater. 282, 112–124 (2000).10.1016/S0022-3115(00)00420-7 ↗
80. ASTM C1220. Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste. ASTM C1220-17 (ASTM, 2017).
81. Jantzen, C. M. & Bibler, N. E. The product consistency test (PCT): how and why it was developed? Ceram. Trans. 207, 155–167 (2009).10.1002/9780470538371.ch15 ↗
82. Ebert, W. L., Bates, J. K., Buck, E. C. & Bradley, C. R. Accelerated glass reaction under PCT conditions. Mater. Res. Soc. Symp. Proc. 294, 569–576 (1993).10.1557/PROC-294-569 ↗
83. Aréna, H., Rébiscoul, D., Garcès, E. & Godon, N. Comparative effect of alkaline elements and calcium on alteration of International Simple Glass. npj Mater. Degrad. 3, 10 (2019).10.1038/s41529-019-0072-7 ↗
84. Utton, C. A. et al. Dissolution of vitrified wastes in a high-pH calcium-rich solution. J. Nucl. Mater. 435, 112–122 (2013).10.1016/j.jnucmat.2012.12.032 ↗
85. Schofield, J. M. et al. Experimental studies of the chemical durability of UK HLW and ILW glasses – interim progress report (AMEC/103498/IPR/02 revision 3) Available at: https://rwm.nda.gov.uk/publication/experimental-studies-of-the-chemical-durability-of-uk-hlw-and-ilw-glasses-interim-progress-report-amec103498ipr02-revision-3/ (2017).
86. Vernaz, E., Advocat, T. & Dussossoy, J. L. Effects of the SA/V ratio on the long-term corrosion kinetics of R7T7 glass. Ceram. Trans. 9, 175–185 (1990).
87. Ebert, W. L. The Effects of the Glass Surface Area/solution Volume Ratio on Glass Corrosion: A Critical Review. ANL-94/34. (Chemical Technical Division, Argonne National Laboratory, 1995).10.2172/67461 ↗
88. ASTM C1663. Standard Test Method for Measuring Waste Glass or Glass Ceramic Durability by Vapor Hydration Test. ASTM C1663-18 (ASTM, 2018).
89. PNNL. Pacific Northwest National Laboratory, Vapor-phase Hydration Test Procedure. GDL-VHT, Rev.1 (Pacific Northwest National Laboratory, 1999).
90. Bouakkaz, R., Abdelouas, A. & Grambow, B. Kinetic study and structural evolution of SON68 nuclear waste glass altered from 35 to 125 °C under unsaturated H2O and D2O18 vapour conditions. Corros. Sci. 134, 1–16 (2018).10.1016/j.corsci.2017.12.035 ↗
91. Narayanasamya, S. et al. Influence of composition of nuclear waste glasses on vapor phase hydration. J. Nucl. Mater. 525, 53–71 (2019).10.1016/j.jnucmat.2019.07.015 ↗
92. Narayanasamy, S., Jollivet, P., Sessegolo, L., Angeli, F. & Abdelouas, A. Influence of temperature and relative humidity on vapor hydration of an AVM nuclear waste glass. J. Nucl. Mater. 543, 152571 (2021).10.1016/j.jnucmat.2020.152571 ↗
93. ANDRA, Dossier 2005 Argile, Tome, Phenomenological Evolution of a Geological Repository, in ANDRA Report C.RP.ADS.04.0025, 1-525 (ANDRA, 2005).
94. Neeway, J. Vapor hydration of SON68 glass from 90 C to 200 C: a kinetic study and corrosion products investigation. J. Non-Cryst. Solids 358, 2894–2905 (2012).10.1016/j.jnoncrysol.2012.07.020 ↗
95. Debure, M., De Windt, L., Frugier, P., Gin, S. & Vieillard, P. Mineralogy and thermodynamic properties of magnesium phyllosilicates formed during the alteration of a simplified nuclear glass. J. Nucl. Mater. 475, 255–265 (2016).10.1016/j.jnucmat.2016.04.008 ↗
96. Bouakkaz, R., Abdelouas, A., El Mendili, Y., David, K. & Grambow, B. Alteration of 29Si-doped SON68 borosilicate nuclear waste glass in the presence of near field materials. Appl. Geochem. 111, 104436 (2019).10.1016/j.apgeochem.2019.104436 ↗
97. De Echave, T., Tribet, M., Gin, S. & Jégou, C. Influence of iron on the alteration of the SON68 nuclear glass in the Callovo-Oxfordian groundwater. Appl. Geochem. 100, 268–278 (2019).10.1016/j.apgeochem.2018.12.007 ↗
98. EPA SW-846. Validated Test Method 1313: Liquid-Solid Partitioning as a Function of Extract pH Using a Parallel Batch Extraction Procedure, Environmental Protection Agency. https://www.epa.gov/hw-sw846/validated-testmethod-1313-liquid-solid-partitioning-function-extract-ph-using-parallel (2017).
99. Thorpe, C. L. et al. Evaluation of Novel Leaching Assessment for Nuclear Waste Glasses – 18314. WM2018 Conference, March 18-22 (Phoenix, Arizona, USA, 2018).
100. EPA SW-846. Test Method 1311: Toxicity Characteristic Leaching Procedure, part of Test Methods for Evaluating Solid Waste, Physical/Chemical Methods. (Environmental Protection Agency, 1992).