Article
Article name Evaluation of Radiation Resistance of Barrier Clay Materials
Authors Chubreev D.O. candidate of physical and mathematical sciences, head of the Laboratory of Engineering Safety Barriers, dimanch@tpu.ru
Bibliographic description Mishankin A. Yu., Chubreev D. O., Pavlyuk A. O., Yazikov E. G. Evaluation of Radiation Resistance of Barrier Clay Materials // Transbaikal State University Journal. 2023. Vol. 29, no. 3. P. 26–34. DOI: 10.2109/2227- 9245-2023-29-3-26-34.
Category Earth and Environmental Sciences
DOI 504
DOI 10.2109/2227-9245-2023-29-3-26-34
Article type Original article
Annotation The article presents data on the experience of studying barrier clay materials on the basis of the laboratory of engineering safety barriers of the Research Center for the Decommissioning of Nuclear and Radiation Hazardous Facilities and a review on the topic of the effect of radiation exposure on various characteristics of barrier clay materials. The object of the study is a barrier clay material based on bentonite clay mined at the 10th Khutor deposit (Ust-Abakansky district of the Republic of Khakassia). The bentonites of this deposit are characterized by volcanic-sedimentary genesis, their main component is montmorillonite, which is of pyroclastic origin. The subjects of the study are such indicators of the quality of barrier clay materials when they are used in engineering safety barriers, such as the mineral and micromineral composition before and after irradiation. The purpose of the study is to assess the effect of radiation exposure on the mineral and micromineral composition of barrier clay materials. In the course of the work, studies were carried out using the methods of powder X-ray diffractometry and scanning electron microscopy with energy-dispersive spectrometry. The objectives of the scientific study included the assessment of the radiation resistance of the barrier clay material at an absorbed dose of gamma radiation of 45–50 MGy. In the course of the work, literature data on the effect of radiation exposure on the properties and characteristics of clay materials were analyzed. Based on the research results, data on the mineral and micromineral composition of barrier clay materials, as well as on the morphology of mineral particles before and after irradiation, were obtained and compared. It is concluded that there is no mineralogical evolution of the substance of the barrier clay material as a result of radiation exposure.
Key words barrier clay material, engineering safety barrier, radiation exposure, radiation resistance, characteris-tics of barrier clay materials, mineral composition, clay minerals, mineral particle morphology, X-ray diffractometry, scanning electron microscopy
Article information
References 1. Dashko R. E., Eremeeva A. A. Analysis and assessment of improving the safety of low-level waste disposal in the Lower Cambrian blue clays of the Western part of the Leningrad region. Notes of the Mining Institute, vol. 154, pp. 131–135, 2003. (In Rus.). 2. Ilyina O. A., Krupskaya V. V., Vinokurov S. E., Kalmykov S. N. Current status in the development and use of clay materials as engineering safety barriers at radioactive waste conservation and disposal facilities in Russia. Radioactive Waste, no. 4, pp. 71–84, 2019. (In Rus.). 3. Kedrovsky O. A., Shishits I. Yu., Gupalo T. A., Leonov E. A., Savushkina M. K., Kosarev I. M. Substantiation of conditions for localization of high-level waste and spent nuclear fuel in geological formations. Atomic Energy, vol. 70, no. 5, pp. 294–298, 1991. (In Rus.). 4. Krupskaya V. V, Zakusin S. V. Determination of the mineral composition of soils by X-ray diffractometry. Laboratory workshop on soil science. Ed. V. A. Koroleva, V. N. Shirokov, V. V. Shanina. Moscow: KDU, Dobrosvet, 2019. (In Rus.). 5. Krupskaya V. V., Zakusin S. V., Lekhov V. A., Dorzhieva O. V., Belousov P. E., Tyupina E. A. Insulation properties of bentonite barrier systems for radioactive waste disposal in the Nizhnekansky massif. Radioactive Waste, no. 1, pp. 35–55, 2020. (In Rus). 6. Martynov K. V., Zakharova E. V., Dorofeev A. N., Zubkov A. A., Prishchep A. A. The use of clay materials to create protective barriers for radiation-hazardous objects. Radioactive Waste, no. 3, pp. 39–53, 2020. (In Rus). 7. Guidelines for X-Ray Investigation of Minerals. Ed. V. A. Frank-Kamensky. Leningrad: Nedra, 1983. (In Rus.). 8. Tsebakovskaya N. S., Utkin S. S., Linge I. I., Pron I. A. Foreign SNF and RW disposal projects. Part I. Current state of projects for the creation of deep geological disposal sites in European countries. Moscow: IBRAE RAN, 2017. (In Rus). 9. Egerton R. F. Physical principles of electron microscopy. Introduction to transmission, scanning and analytical electron microscopy. Moscow: Technosfera, 2010. (In Rus.). 10. Allard T., Calas G. Radiation effects on clay mineral properties. Applied Clay Science, vol. 43, pp. 143– 149, 2009. (In Eng.). 11. Baborova L., Vopalka D. Migration Behaviour of Strontium in Czech Bentonite Clay. Journal of Sustainable Development of Energy, Water and Environment Systems, vol. 4, pp. 293–306, 2016. (In Eng). 12. Dies J., de las Cuevas C., Tarrasa F., Miralles L., Pueyo J. J., Santiago J. L. Thermoluminescence response of heavily irradiated calcic bentonite. Radiation Protection Dosimetry, vol. 85, pp. 481–486, 1999. (In Eng.). 13. Ewing R. C., Weber W. J., Clinard F. W. J. Radiation effects in nuclear waste forms for high-level radioactive waste. Progress in Nuclear Energy, vol. 29, no. 2, pp. 63–127, 1995. (In Eng.). 14. Pusch R. Waste disposal in rock. Developments in Geotechnical Engineering. Elsevier, Amsterdam, vol. 76, pp. 57–68, 1994. (In Eng.). 15. Wang S. X., Wang L. M., Ewing R. C. Electron and ion irradiation of zeolites. Journal of Nuclear Materials, vol. 278, pp. 233–241, 2000. (In Eng.).
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