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Estimation of radionuclides leaching characteristics in different sized geopolymer waste forms with simulated spent ion-exchange resin

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초록

This study presents a method to solidify spent ion-exchange resin (IER) in a metakaolin-based geopolymer and shows results of mechanical strength, immersion, leaching, irradiation, and thermal cycling tests for waste acceptance criteria (WAC) to repository. The geopolymer waste form with 20 wt% of simulated spent IER met the WAC in South Korea (ROK), and the leaching tests of various sized-waste forms up to 15.0  30.0 cm and waste loadings up to 20 wt% for 1e5 d and 1e90 d achieved a leachability index, Li > 6. In a leaching test for 5 d, the cumulative fraction leached (CFL) for Cs, which leached the most, was linearly correlated with the square root of leaching time for all waste forms, and Li increased as the size of the waste form increased. The CFL was also correlated with elapsed time in the 90 d leaching test. The correlations among CFL, time, and volume-to-surface area ratio of waste forms used to estimate the Li of Cs of a 200-L sized geopolymer with 15 wt% IER showed the Li values as 14.73 (5 d) and 17.71 (90 d), respectively, indicating that the large-sized geopolymer waste form met the WAC.

Abstract

This study presents a method to solidify spent ion-exchange resin (IER) in a metakaolin-based geopolymer and shows results of mechanical strength, immersion, leaching, irradiation, and thermal cycling tests for waste acceptance criteria (WAC) to repository. The geopolymer waste form with 20 wt% of simulated spent IER met the WAC in South Korea (ROK), and the leaching tests of various sized-waste forms up to 15.0  30.0 cm and waste loadings up to 20 wt% for 1e5 d and 1e90 d achieved a leachability index, Li > 6. In a leaching test for 5 d, the cumulative fraction leached (CFL) for Cs, which leached the most, was linearly correlated with the square root of leaching time for all waste forms, and Li increased as the size of the waste form increased. The CFL was also correlated with elapsed time in the 90 d leaching test. The correlations among CFL, time, and volume-to-surface area ratio of waste forms used to estimate the Li of Cs of a 200-L sized geopolymer with 15 wt% IER showed the Li values as 14.73 (5 d) and 17.71 (90 d), respectively, indicating that the large-sized geopolymer waste form met the WAC.

참고문헌 (46)

  1. IAEA, "Nuclear Power Reactors in the World, vol. 2" (2022), IAEA
  2. IAEA, "Status and Trends in Spent Fuel and Radioactive Waste Management" (2022), IAEA
  3. M. H. Ahn, "Disposal concept for LILW in Korea : characterization methodology and the disposal priority", Prog. Nucl. Energy, 51(2), pp.327~333 (2009)
  4. S.Y. Kang, "Competitive adsorption characteristics of Co2+, Ni2+, and Cr3+ by IRN-77 cation exchange resin in synthesized wastewater", Chemosphere, 56(2), pp.141~147 (2004)
  5. J. Wang, "Treatment and disposal of spent radioactive ion-exchange resins produced in the nuclear industry", Prog. Nucl. Energy, 78, pp.47~55 (2015)
  6. Radioactive Waste Streams: Waste Classification for Disposal, CRS Report for Congress, "A. Andrews", Congressional Research Service, ~ (2006)
  7. W. Lin, "Performance study of ion exchange resins solidification using metakaolin-based geopolymer binder", Prog. Nucl. Energy, 129, pp.103508~ (2020)
  8. Final Safety Analysis Report, Shin Kori Unit 3 & 4, "Korea Hydro & Nuclear Power Co Ltd", ~ (2018)
  9. Nursaidatul Syafadillah Kamaruzaman, "Management of Spent Ion-Exchange Resins From Nuclear Power Plant by Blending Method", Journal of Nuclear Fuel Cycle and Waste Technology, 16(1), pp.65~82 (2018), 한국방사성폐기물학회[DOI]
  10. V. Luca, "Cation immobilization in pyrolyzed simulated spent ion exchange resins", J. Nucl. Mater, 424(1-3), pp.1~11 (2012)
  11. L. Shao, "In situ immobilization properties and mechanism of geopolymer microspheres after adsorbing Sr2þand Cs+ (Sr", Cs@ GPMs), 2023, pp.49(7), 10807~10821
  12. H. Lei, "Facile fabrication of metakaolin", slag-based zeolite microspheres (M, J. Hazard Mater, pp.2021, 406[DOI]
  13. ANTIOXIeDecontamination Techniques for Activity Removal in Nuclear Environments, "P. Kinnunen", VTT Technical Research Centre of Finland, ~, pp.VTT-R-00299-08 (2008)
  14. J. Li, "Advances in cement solidification technology for waste radioactive ion exchange resins : a review", J. Hazard Mater, 135(1-3), pp.443~448 (2006)
  15. M. Bortnikova, "Conditioning the slag formed during thermochemical treatment of spent ion-exchange resins", At. Energy, 105(5), pp.351~356 (2008)
  16. J. Ahn, "Development of metakaolin-based geopolymer for solidification of sulfate-rich HyBRID sludge waste", J. Nucl. Mater, 518, pp.247~255 (2019)
  17. T. A. Bayoumi, "Immobilization of sulfate waste simulate in polymerecement composite based on recycled expanded polystyrene foam waste : Evaluation of the final waste form under freezeethaw treatment", Polym. Compos, 38(4), pp.637~645 (2017)
  18. W. H. Lee, "Geopolymer technology for the solidification of simulated ion exchange resins with radionuclides", J. Environ. Manag, 235, pp.19~27 (2019)
  19. E. Lafond, "Investigation of the swelling behavior of cationic exchange resins saturated with Naþ ions in a C3S paste", Cement Concr. Res, 69, pp.61~71 (2015)
  20. J. Davidovits, "Properties of Geopolymer Cements", First International Conference on Alkaline Cements and Concretes, pp.131~149 (1994), Kiev State Technical University Kiev
  21. C. A. Rees, "The mechanism of geopolymer gel formation investigated through seeded nucleation", Colloids Surf. A Physicochem. Eng. Asp, 318(1-3), pp.97~105 (2008)
  22. P. Duan, "An investigation of the microstructure and durability of a fluidized bed fly ashemetakaolin geopolymer after heat and acid exposure", Mater. Des, 74, pp.125~137 (2015)
  23. Kim Byoungkwan, "Review on characteristics of metakaolin-based geopolymer and fast setting", 한국세라믹학회지, 57(4), pp.368~377 (2020), 한국세라믹학회[DOI]
  24. J. G. Jang, "Physical barrier effect of geopolymeric waste form on diffusivity of cesium and strontium", J. Hazard Mater, 318, pp.339~346 (2016)
  25. M. L. Yeoh, "Mechanistic impacts of long-term gamma irradiation on physicochemical, structural, and mechanical stabilities of radiation-responsive geopolymer pastes", J. Hazard Mater, 407, pp.124805~ (2021)
  26. P. He, "Interplay between storage temperature, medium and leaching kinetics of hazardous wastes in Metakaolin-based geopolymer", J. Hazard Mater, 384, pp.121377~ (2020)
  27. M. I. Ojovan, "Long-term field and laboratory leaching tests of cemented radioactive wastes", J. Hazard Mater, 187(1-3), pp.296~302 (2011)
  28. Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure, "American Nuclear Society", American Nuclear Society La Grange Park, ~, pp.ANSI (2003), ANS-16.1-2003
  29. Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure, "American Nuclear Society", American Nuclear Society La Grange Park, ~, pp.ANSI (2019), ANS-16.1-2019
  30. C. McIsaac, "Effect of waste form size on the leachability of radionuclides contained in cement-solidified evaporator concentrates generated at nuclear power stations", Waste Manage. (Tucson, Ariz.), 11(4), pp.271~282 (1991)
  31. B. Kim, "Development of geopolymer waste form for immobilization of radioactive borate waste", J. Hazard Mater, 419, pp.126402~ (2021)
  32. Standard Test Method for Compressive Strength of Concrete, "Korean Standards Association", ~, pp.KS F 2405 (2010)
  33. Technical Position on Waste Form (Rev. 1), "US Nuclear Regulatory Commission", Low-Level Waste Management Branch, Office of Nuclear Material Safety and Safeguards, ~ (1991)
  34. Standard Test Method for Thermocycling of Electroplated Plastics, "American Society for Testing and Materials", ASTM, ~ (1985)
  35. R. Pouhet, "Influence of the initial water content in flash calcined metakaolin-based geopolymer", Construct. Build. Mater, 201, pp.421~429 (2019)
  36. S. V. Patankar, "Effect of water-to-geopolymer binder ratio on the production of fly ash based geopolymer concrete", Int. J. Adv. Technol. Civ. Eng, 2(1), pp.79~83 (2013)
  37. D. Hardjito, "Factors influencing the compressive strength of fly ash-based geopolymer concrete", Civ. Eng. Dimens, 6(2), pp.88~93 (2004)
  38. N. Zhang, "Specimen size effects on the mechanical behaviors and failure patterns of the mine tailings-based geopolymer under uniaxial compression", Construct. Build. Mater, 281, pp.122525~ (2021)
  39. P. Chen, "Size effect on peak axial strain and stress-strain behavior of concrete subjected to axial compression", Construct. Build. Mater, 188, pp.645~655 (2018)
  40. Y. Sherif, "Effect of aggregate type and specimen configuration on concrete compressive strength", Crystals, 10(7), pp.625~ (2020)
  41. D. Lambertin, "Influence of gamma ray irradiation on metakaolin based sodium geopolymer", J. Nucl. Mater, 443(1-3), pp.311~315 (2013)
  42. Solubility of Radionuclides in a Concrete Environment for Provisional Safety Analyses for SGT-E2, "U. Berner", Nagra, ~, pp.TNB 14-07 (2014)
  43. X. Niu, "Adsorption behaviour of simulant radionuclide cations and anions in metakaolin-based geopolymer", J. Hazard Mater, 429, pp.128373~ (2022)
  44. S. Foster, "Binding mechanism of strontium to biopolymer hydrogel composite materials", J. Radioanal. Nucl. Chem, 332(5), pp.1577~1582 (2023)
  45. A.J. Chandler, "Municipal Solid Waste Incinerator Residues" (1997), Elsevier
  46. G. J. de Groot, "Determination of Leaching Characteristics of Waste Materials Leading to Environmental Product Certification", ASTM Special Technical Publication, 1123, pp.149~170 (1992)

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