Leaching behavior of HLW glass waste form in Beishan groundwater environment
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OpenAlex topics: Nuclear materials and radiation effects · CO2 Sequestration and Geologic Interactions · Glass properties and applications
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References (42)
Show source-provided references
1. Research on container for high-level radioactive waste vitrification product10.1016/j.jandt.2025.06.005 ↗
2. The rock outcrop joint identification for the Beishan high-level radioactive waste disposal underground research laboratory based on Deep learning
3. Progress on rock mechanics research of Beishan granite for geological disposal of high-level radioactive waste in China10.1016/j.rockmb.2023.100046 ↗
4. Glass materials road map for radioactive waste immobilization10.1007/s13538-024-01540-9 ↗
5. Forty years of durability assessment of nuclear waste glass by standard methods10.1038/s41529-021-00210-4 ↗
6. Radionuclides containment in nuclear glasses: an overview10.1515/ract-2016-2658 ↗
7. A comparative review of the aqueous corrosion of glasses, crystalline ceramics, and metals10.1038/s41529-018-0037-2 ↗
8. C.M. Jantzen, Development of glass matrices for high level radioactive wastes, handbook of advanced radioactive waste conditioning technologies, (2011) 230–292, doi:10.1533/9780857090959.2.230.10.1533/9780857090959.2.230 ↗
9. M.I. Ojovan, Performance of wasteform materials, an introduction to nuclear waste immobilisation, (2019) 433–461, doi:10.1016/B978-0-08-102702-8.00023-6.10.1016/B978-0-08-102702-8.00023-6 ↗
10. Uranium retention in silica-rich natural glasses: nuclear waste disposal aspect10.3390/ceramics6020069 ↗
11. The influence of radiation on confinement properties of nuclear waste glasses
12. Applying laboratory methods for durability assessment of vitrified material to archaeological samples10.1038/s41529-021-00204-2 ↗
13. On the effect of Al on alumino-borosilicate glass chemical durability
14. Effect of na₂o on aqueous dissolution of nuclear waste glasses10.1016/j.jnucmat.2017.02.013 ↗
15. Vapor hydration of SON68 glass from 90 °C to 200 °C: a kinetic study and corrosion products investigation10.1016/j.jnoncrysol.2012.07.020 ↗
16. Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste, npj Mater
17. Synthesis and characterization of multi-component borosilicate glass beads for radioactive liquid waste immobilisation10.1016/j.jnucmat.2024.155485 ↗
18. SON68 nuclear glass dissolution kinetics: current state of knowledge and basis of the new GRAAL model10.1016/j.jnucmat.2008.06.044 ↗
19. SON68 nuclear glass dissolution kinetics: current state of knowledge and basis of the new GRAAL model10.1016/j.jnucmat.2008.06.044 ↗
20. Characterization and modeling of chemical reactions taking place during the vitrification of high level nuclear waste10.1016/j.jnucmat.2022.153878 ↗
21. SON68 glass dissolution driven by magnesium silicate precipitation10.1016/j.jnucmat.2013.08.029 ↗
22. Sol-gel transition effect based on konjac glucomannan thermosensitive hydrogel for photo-assisted uranium extraction10.1016/j.scib.2024.07.005 ↗
23. Photo-assisted uranium extraction based on heterogeneous catalysts10.1016/j.scib.2024.09.039 ↗
24. Regional groundwater flow assessment in a prospective high-level radioactive waste repository of China
25. Using multiple isotopes to determine groundwater source, age, and renewal rate in the Beishan preselected area for geological disposal of high-level radioactive waste in China10.1016/j.jhydrol.2023.130592 ↗
26. Experimental study on cycle property of groundwater in fractured granite in Beishan, China
27. Safety assessment in the disposal of high-level radioactive wastes (HLWs): a geochemical study of uranium complexes in deep groundwater in granites from Beishan10.1007/s10967-024-09413-w ↗
28. Solubility, speciation and sorption calculation of americium in far-field and near-field Beishan groundwaters
29. Effect of Beishan groundwater salinity on the self-sealing performance of compacted GMZ bentonite
30. Effect of wet-dry cycling on swelling and hydraulic conductivity of GCLs10.1061/(ASCE)1090-0241(2000)126:1(40) ↗
31. Research of the corrosion behaviour of X65 low carbon steel in aerobic Gaomiaozi bentonite saturated with Beishan groundwater, in: asian Forum Mater
32. ASTM C1220-21, Standard test method for static leaching of monolithic waste forms for disposal of radioactive waste, 2021.
33. Leach rate studies on glass containing actual radioactive waste10.1016/0191-815X(82)90055-9 ↗
34. Dissolution of vitrified wastes in a high-pH calcium-rich solution10.1016/j.jnucmat.2012.12.032 ↗
35. Reevaluating the efficacy of moderate annealing in nuclear waste vitrification for sustainable high-level waste management10.1016/j.jclepro.2020.122155 ↗
36. Structural investigation of ternary La/alkaline earth phosphate (La₁₋ₓMₓP₃Oᵧ) (M = Ba, Ca, Sr) glasses10.1016/j.jnoncrysol.2009.04.023 ↗
37. Structural investigations on 20MO-xBi₂O₃-(80-x)B₂O₃ (M = Ca, Sr and Ba; x=15 and 55) glasses10.1016/j.jnoncrysol.2011.08.002 ↗
38. Relating Magnox and international waste glasses10.1016/j.jnoncrysol.2019.119647 ↗
39. Long-term product consistency test of simulated 90-19/Nd HLW glass10.1016/j.jnucmat.2010.11.020 ↗
40. Nd³⁺-doped lithium fluoro lanthanum oxy lead borate glass ceramics: a novel platform for high-temperature optoelectronic and radiation shielding systems10.1016/j.radphyschem.2025.112957 ↗
41. Microstructural evolution of sealing glass materials with varied concentrations of B₂O₃ and SrO10.1016/j.jnoncrysol.2025.123597 ↗
42. Examining correlations between the dissolution rates and optical basicity of modified aluminoborate glasses10.1111/jace.20402 ↗