Yu. A. Olkhovyk
SI “The Institute of Environmental Geochemistry
of the National Academy of Sciences of Ukraine”,
34a, Palladin ave, Kyiv, 03142, Ukraine
DOI: doi.org/10.31717/2311-8253.20.3.6
Abstract
The existing world experience of practical use of sorption technology and technology of cementing liquid borne radioactive waste of nuclear power plants (NPP) with water-water energetic reactors (WWER) to obtain a product 1suitable for transfer to disposal facilities is considered. It has been concluded that salt cake accumulated in NPP storage facilities is a major problem that determines the further choice of the development and implementation of conditioning technologies. Currently, 18,000 salt cake containers stored at the Zaporizhzhia NPP and Khmelnitskiy NPP storage facilities have exceeded their design life. A possible solution is to change the classification of the salt cake and to classify it as solid radioactive waste. It is noted that the existing tax system for the generation of radioactive waste in Ukraine does not contribute to the choice of conditioning technologies aimed at minimizing the volume of the final product. The prospect of application of the technology of melting in the “cold crucible” for one-stage formation from a evaporator bottoms and salt cake borosilicate glass, guaranteed capable in the conditions of surface disposal to ensure the isolation of radionuclides during the time required for decay to a safe level of radioactivity. It is proposed to create a melting unit according to the modular scheme, when several parallel crucibles with capacity up to 20 kg/h with cheaper highfrequency generators with a capacity of 160 kW are connected to common ventilation system. The urgency of carrying out technical and economic analysis to determine the optimal 56 ISSN 2311-8253 Nuclear Power and the Environment № 3 (18) 2020 solutions for the introduction of effective and economically sound technologies for the processing of evaporator bottoms and salt cake at Ukrainian NPPs is emphasized.
Keywords: liquid radioactive waste, evaporator bottoms, salt cake, sorption, cementing, borosilicate glass, conditioning.
References
1. Management of radioactive waste during the operation of NPP of NNEGC “Energoatom” (as of 31.12.2018). [Electronic resource]. Available
at: http://www.energoatom.com.ua/en/actvts-16/nuclear-88/radiation_safety-89/radioactive_waste-92/p/informacia_sodo_povodzenna_z_radioactive_vidhodami_pri_ekspluatacii_aes_dp_naek_energoatom_.128_1. (in Ukr.)
2. Basic sanitary rules for ensuring radiation safety of Ukraine: State sanitary rules 6.177-2005-09-02 (OSPU-2005). Approved by the Order of the Ministry of Health of Ukraine dated 02.02.2005. (in Ukr.)
3. Uzikov V. A. (2017). Non-reagent technology for concentrating LRW and other solutions. Available at:http://www.proatom.ru/modules.php?name=News&file=print&sid=7531. (in Russ.)
4. Letter of SE NNEGC “Energoatom” dated 09.01.2018 № 9-КФ, confidential.
(in Ukr.)
5. The Law of Ukraine “On Radioactive Waste Management” No. 255/95-VR dated 30.06.1995. Kyiv: Database of “Legislation of Ukraine” of the Verkhovna Rada of Ukraine; 2018. Available at: http://zakon3.rada.gov.ua/laws/ show/255/95-%D0%B2%D1%80. (in Ukr.)
6. Avezniyazov S. R., Stakhiv M. R. (2018). [Experience in LWW management at Kola NPP]. Radioaktivnye othody [Radioactive waste], vol. 5, no. 4, pp. 49−55.
(in Russ.)
7. Povarov V. P. (2012). [Sources of LRW formation at the Novovoronezh NPP and prospects for reducing the dynamics of their accumulation]. Proceedings of the 8th International scientific and technical conference “Hydro-chemical regime of the NPP” (Moscow, October 23−25, 2012), p. 215. (in Russ.)
8. Nikiforov A. S., Kulichenko V. V., Zhikharev M. I. (1985). Obezvrezhivanie zhidkih radioaktivnyh othodov [Disposal of liquid radioactive waste]. Moscow: Energoatomizdat, 184 p. (in Russ.)
9. Svidersky V. A., Glukhovsky V. V., Glukhovsky I. V., Dashkova T. S. (2019). [Technologies of solidification of liquid radioactive waste] Yaderna ta radiatsiyna bezpeka [Nuclear and radiation safety], vol. 81, no. 1, 68−79. (in Russ.)
10. Petrova T. M. (1997). [Concrete for transport construction on the basis of cementless cement] (Dr. Dissertation). Saint Petersburg: State University of Communication, 537 p. (in Russ.)
11. Skomorokhova S. N., Bogdanovich N. G., Konovalov E. E., Korchagin Yu. P., Arefiev E. K., Kochnov Y. K. (2010). [Development of cementing technology for conditioning RW] Bezopasnost’ okruzhayushchey sredy [Environmental safety], no. 3, pp. 75−80. (in Russ.)
12. Maslov M. V., Gupalo B. C., Chistyakov V. N. (2012). [Study of schemes for handling accumulated radioactive waste with a view to their preparation for final isolation] Gornyy informatsionno analiticheskiy byulleten’ [Mountain Information and Analytical Bulletin], no. 1, pp. 160−164. (in Russ.)
13. Draft Order of the Ministry of Health of Ukraine “On Amendments to the Basic Sanitary Rules for Ensuring Radiation Safety of Ukraine”. Available at: http://old.moz.gov.ua/en/print/dn_20151214_0.html. (in Ukr.)
14. Kashcheev V., Musatov N., Ojovan M. (2020). Advanced vitreous wasteforms for radioactive salt cake waste immobilization. MRS Advances, vol. 5, no. 3−4,
pp. 121−129. DOI: 10.1557/adv.2020.45.
15. Olkhovyk Yu. (2014). Vitrification of liquid boron-containing radioactive wastes produced by NPPS. Australian Journal of Scientific Research, vol. 5, no. 1, pр. 411−416.
16. Laverov N. P., Omelyanenko B. I., Yudintsev S. V., Stefanovsky S. V., Nikonov B. S. (2013). [Glasses for immobilization of low and medium level radioactive waste]. Geologiya rudnykh mestorozhdeniy [Geology of oredeposits], vol. 55, no. 2,
pp. 87−113. (in Russ.)
17. Flament T., Brunelot P. (2001). The cold crucible vitrification pilot plant: a key facility for the vitrification of the waste produced in the Korean nuclear power plant. Proceedings of the WM’01 Conference (Tucson, USA, February 25 — March 1,2001). Available at: https://pdfs.semanticscholar.org/d453/
66d0b01a1be49b643b9035d45400481832cf.pdf?_ga=2.231354521.729762844.1595412236-1596455350.1595412236.
18. Olkhovyk Yu. O. (2016). [Regarding the technological support for the sheltering of lava fuel containing the Shelter] Yaderna enerhetyka ta dovkillya [Nuclear Power and the Environment], vol. 8, no. 2, pp. 53−57. (in Ukr.)
19. Recommendations on Establishment of Criteria for Acceptance of Air-Conditioned Radioactive Waste for Landfill Disposal (RD306.4.098-2004). Approved by the Order of the State Committee for Nuclear Regulation of Ukraine No. 160 dated 25.10.2004. (in Ukr.)
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