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Immobilize CeO2 as simulated nuclear waste in natural magmatic granite: maximum solid solubility

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Abstract

The radionuclides are extracted from the minerals which make up the rocks. This work takes natural magmatic granite as the matrix and CeO2 as the simulated radioactive waste to explore the maximum solid solubility. After analyzing the phase transition of pure granite with varied temperatures, the solidification was carried out at 1300 ℃. The phase, microstructure, element distribution, hardness and chemical stability of the solidified bodies were studied. The results showed that the maximum solid solubility was up to 8 wt.%. The normal leaching rate of Ce4+ after the first 3 d was about 3.89 × 10–7 g·m−2·d−1.

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References

  1. Bol’Shov LA, Linge II (2020) Strategy for the development of nuclear energy in russia and environmental matters. At Energ 127(4):333–338

    Article  CAS  Google Scholar 

  2. Gyamfi K, Birikorang SA, Ampomah-Amoako E et al (2015) The choice of nuclear energy for ghana as a result of development of its energy production. J Energy 2020(2020):1–6

    Google Scholar 

  3. Kaushik CP, Shah JG (2010) Challenges in Development of Matrices for Vitrification of High-level Radioactive Waste. BARC News Lett 314:20–27

    CAS  Google Scholar 

  4. Peters T B, Poirier M R, Fondeur F F, et al. (2009) Separation of Fission Products and Actinides From Savannah River Site High-Level Nuclear Wastes[C]// ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management.

  5. Amiro BD (2003) Environmental radioactivity. In: Encyclopedia of physical science & technology, 3rd edn. Academic Press, pp 583–599

  6. Briggs S, Mckelvie J, Sleep B et al (2017) Multi-dimensional transport modelling of corrosive agents through a bentonite buffer in a Canadian deep geological repository. Sci Total Environ 599–600:348–354

    Article  Google Scholar 

  7. Malkovsky VI, Yudintsev SV, Sharaputa MK et al (2019) Influence of buoyancy forces on movement of liquid radioactive waste from deep injection disposal site in the Tomsk region, Russian Federation: analytical estimate and numerical modeling. Environ Earth Sci. https://doi.org/10.1007/s12665-019-8209-0

    Article  Google Scholar 

  8. Yuan XN, Zhang ZT, Cai XN et al (2015) Development of Glass-based Confinement Matrix for Plutonium-containing Waste. Atomic Energy ence Technol 49(2):240–249

    CAS  Google Scholar 

  9. Tang H, Shu X, Huang W et al (2021) Rapid solidification of Sr-contaminated soil by consecutive microwave sintering: mechanism and stability evaluation. J Hazard Mater 407:124761

    Article  CAS  Google Scholar 

  10. Shu X, Chen S, Hou C et al (2020) Rapid synthesis of Gd2Zr2O7 glass-ceramics using spark plasma sintering. J Am Ceram Soc 103(1):1–7

    Article  Google Scholar 

  11. Zhang J, Wang J, Gao D et al (2021) Enhanced energy storage performances of CaTiO3-based ceramic through A-site Sm3+ doping and A-site vacancy. J Eur Ceram Soc 41(1):352–359

    Article  CAS  Google Scholar 

  12. Valiev D, Babkina AN, Zyryanova KS et al (2020) Radiation-induced processes in alkali-alumina-borate glass-ceramics doped with Cr3+ ions. J Non-Cryst Solids 534:119947

    Article  CAS  Google Scholar 

  13. Barth N, George D, Bouyer F et al (2020) An inverse method predicting thermal fluxes in nuclear waste glass canisters during vitrification and cooling. Nucl Eng Design 1(364):110686

    Article  Google Scholar 

  14. Maletaškić J, Matović B, Stanković N et al (2017) Phase Evolution of Sphene Based Ceramics during Annealing. Energy Procedia 131:407–412

    Article  Google Scholar 

  15. Ringwood AE, Kesson SE, Ware NG et al (1979) Immobilization of High Level Reactor Wastein Synroc. Nat (London) 3(278):219–223

    Article  Google Scholar 

  16. Omel’yanenko Livshits Yudintsev BITSSV et al (2007) Natural and artificial minerals as matrices for immobilization of actinides. Geo Ore Deposits 49(3):173–193

    Article  Google Scholar 

  17. Papadopoulos A, Christofides G, Koroneos A et al (2013) Natural radioactivity and radiation index of the major plutonic bodies in Greece. J Environ Radioact 124:227–238

    Article  CAS  Google Scholar 

  18. Pavlidou S, Koroneos A, Papastefanou C et al (2006) Natural radioactivity of granites used as building materials. J Environ Radioact 89(1):48–60

    Article  CAS  Google Scholar 

  19. Tsai S-C, Wang T-H, Li M-H, Wei Y-Y, Teng S-P (2009) Cesium adsorption and distribution onto crushed granite under different physicochemical conditions. J Hazard Mater 161(2–3):854–861

    Article  CAS  Google Scholar 

  20. Li H, He B, Li P et al (2019) Adsorption behaviors of Eu(III) on granite: batch, electron probe micro-analysis and modeling studies. Environ Earth Sci 78:249

    Article  Google Scholar 

  21. Witherspoon PA, Gale JE, Cook NGW (1979) Investigations in granite at Stripa, Sweden for nuclear waste storage. Lawrence Berkeley Natl Lab 32(6):371–372

    Google Scholar 

  22. Ling H, Wang J, Tang Z et al (2018) The site selection and safety assessment for geological disposal of high level radioactive waste in granite. J Univ South China Sci Technol 32(05):38–43

    Google Scholar 

  23. Pingsheng X (2015) Major elements geochemical characteristics of the granite-type laterite profile in gan xian, jiangxi province. Geol J China Univ 21(03):553–558

    Google Scholar 

  24. Lu X, Chen S, Shu X et al (2018) Immobilisation of nuclear waste by microwave sintering with a natural magmatic rock. Philos Mag Lett 98(4):155–160

    Article  CAS  Google Scholar 

  25. Lu X, Cui C, Song G et al (2011) Capability of zircon as radioactive waste forms for immobilizing tetravalent actinides. China Environ Sci 6:012

    Google Scholar 

  26. Jiali X, Kuibao Z, Zongsheng H et al (2018) Rapid disposal of simulated Ce-bearing radioactive soil waste using self-propagating synthesized zirconolite-rich waste matrice. Ceram Int 44(12):14534–14540

    Article  Google Scholar 

  27. Chen S, Liu X, Shu X et al (2018) Rapid synthesis and chemical durability of Gd2Zr2-xCexO7 via SPS for nuclear waste forms. Ceram Int 44(16):20306–20310

    Article  CAS  Google Scholar 

  28. Zhu JC, Xie CF, Zhang PH, Yang C, Gu CY (2005) Niumiao and Tong’an intrusive bodies of NE Guangxi:Petrology, zircon SHRIMP U-Pb geochronology ang geocheistry. Acta Petrologica Sinica 21(3):665–676

    CAS  Google Scholar 

  29. ASTM C1285–2002(2008), Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: the Product Consistency Test (PCT) [S].

  30. Ahmad S, Mahmoud MM, Seifert HJ (2019) Crystallization of two rare-earth aluminosilicate glass-ceramics using conventional and microwave heat-treatments. J Alloys Compd 797:45–57

    Article  CAS  Google Scholar 

  31. Kucharczyk S, Sitarz M, Zajac M et al (2018) The effect of CaO/SiO2 molar ratio of CaO-Al2O3-SiO2 glasses on their structure and reactivity in alkali activated system. Spectrochim Acta Part A Mol Biomol Spectrosc 194:163–171

    Article  CAS  Google Scholar 

  32. Rao CS, Ravikumar V, Srikumar T et al (2011) The role of coordination and valance states of tungsten ions on some physical properties of Li2O–Al2O3–ZrO2–SiO2 glass system. J Non-Cryst Solids 357(16):3094–3102

    Article  CAS  Google Scholar 

  33. Wang M, Cheng J, Li M et al (2011) Raman spectra of soda–lime–silicate glass doped with rare earth. Physica B 406(20):3865–3869

    Article  CAS  Google Scholar 

  34. Xie Y, Fan L, Shu X et al (2017) Chemical stability of Ce-doped zircon ceramics: influence of pH, temperature and their coupling effects. J Rare Earths 35(2):164–171

    Article  CAS  Google Scholar 

  35. Hodoroaba V-D (2020) Chapter 4.4 - Energy-dispersive X-ray spectroscopy (EDS). In Micro and nano technologies, characterization of nanoparticles. Elsevier, pp 397–417

  36. Wang Z, Cheng L (2014) Effects of doping CeO2/TiO2 on structure and properties of silicate glass. J Alloy Compd 597:167–174

    Article  CAS  Google Scholar 

  37. Scannell G, Laille D, Célarié F et al (2017) Interaction between deformation and crack initiation under Vickers indentation in Na2O-TiO2-SiO2 glasses. Front Mater 4:6

    Article  Google Scholar 

  38. Tiegel M, Hosseinabadi R, Kuhn S et al (2015) Young׳ s modulus, Vickers hardness and indentation fracture toughness of alumino silicate glasses. Ceram Int 41(6):7267–7275

    Article  CAS  Google Scholar 

  39. Shu X, Chen S, Huang W et al (2020) Immobilization of simulated An4+ in radioactive contaminated clay via microwave sintering. Mater Chem Phys 254:123534

    Article  CAS  Google Scholar 

  40. Xue J, Zhang K, He Z et al (2018) Rapid disposal of simulated Ce-bearing radioactive soil waste using self-propagating synthesized zirconolite-rich waste matrice. Ceram Int 44:14534–14540

    Article  CAS  Google Scholar 

  41. Shu X, Huang W, Shi K et al (2021) Microwave vitrification of simulated radioactively contaminated soil: mechanism and performance. J Solid State Chem 293:121757

    Article  CAS  Google Scholar 

Download references

Acknowledgements

The authors appreciate the financial supports from the National Natural Science Foundation of China (No. 21976146) and the Research Fund Program of Guangdong Key Laboratory of Radioactive and Rare Resource Utilization (No.2019-LRRRU02).

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Correspondence to Xiaoyan Shu or Xirui Lu.

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I would like to declare on behalf of my co-authors that this work described is an original research that has not been published previously and is not under consideration for publication elsewhere, in whole or in part. No conflict of interest exits in the submission of this manuscript, and the publication of this manuscript is approved by all authors.

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Li, L., Shu, X., Tang, H. et al. Immobilize CeO2 as simulated nuclear waste in natural magmatic granite: maximum solid solubility. J Radioanal Nucl Chem 328, 795–803 (2021). https://doi.org/10.1007/s10967-021-07691-2

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  • DOI: https://doi.org/10.1007/s10967-021-07691-2

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