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14C in Radioactive Waste for Decommissioning of the Ignalina Nuclear Power Plant

Published online by Cambridge University Press:  09 February 2016

Violeta Vaitkevičiene ,
Jonas Mažeika ,
Žana Skuratovič ,
Stasys Motiejūnas ,
Algirdas Vaidotas ,
Aleksandr Oryšaka  and
Sergej Ovčinikov
Violeta Vaitkevičiene*
Affiliation:
Lithuanian Energy Institute, Laboratory of Nuclear Engineering, Breslaujos 3, 03219 Kaunas, Lithuania Vytautas Magnus University, Department of Biochemistry and Biotechnologies, Vileikos 8, LT-44404 Kaunas, Lithuania
Jonas Mažeika
Affiliation:
Nature Research Centre, Institute of Geology and Geography, T. Ševčenkos 13, 03223 Vilnius, Lithuania
Žana Skuratovič
Affiliation:
Nature Research Centre, Institute of Geology and Geography, T. Ševčenkos 13, 03223 Vilnius, Lithuania
Stasys Motiejūnas
Affiliation:
Radioactive Waste Management Agency, P. Lukšio 5, 08221 Vilnius, Lithuania
Algirdas Vaidotas
Affiliation:
Radioactive Waste Management Agency, P. Lukšio 5, 08221 Vilnius, Lithuania
Aleksandr Oryšaka
Affiliation:
Ignalina Nuclear Power Plant, Visaginas municipality, 31500, Lithuania
Sergej Ovčinikov
Affiliation:
Ignalina Nuclear Power Plant, Visaginas municipality, 31500, Lithuania
*
2Corresponding author. Email: [email protected].
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Abstract

Radiocarbon is one of the most significant radionuclides affecting the safety margins of near-surface repositories for the disposal of low- and intermediate-level, short-lived radioactive waste, arising from the operation and decommissioning of nuclear power plants (NPPs). One of the goals of the present study was to characterize radioactive waste from Ignalina NPP (Lithuania) (storage tanks TW18B01 and TW11B03) from the spent ion-exchange resins/perlite stream to determine the 14C-specific activity of inorganic and organic carbon compounds. The approach applied is based on classical radiochemical separation methods, including acid-stripping techniques and wet oxidation with subsequent catalytic combustion. The suitability of the method for 14C-specific activity determination in ion-exchange resin samples with a minimum detectable activity of 0.5 Bq/g by liquid scintillation counting (LSC) was demonstrated. The extraction efficiency of inorganic and organic carbon compounds based on model samples with known 14C activity was estimated. The fraction of 14C associated with organic compounds ranged from 42% to 63% for storage tank TW18B01 and from 30% to 63% for storage tank TW11B03. The specific activity of inorganic 14C was estimated as 12.6 Bq/g with a relative standard deviation (RSD) of 29% for storage tank TW18B01, and 177.5 Bq/g with a RSD of 35% for storage tank TW11B03. Based on volume and density data, the total 14C activity for radioactive waste stored in tanks TW18B01 and TW11B03 was estimated as 3.59E + 10 Bq (±32%) and 4.15E + 11 Bq (±28%), respectively.

Type
Articles
Information
Radiocarbon , Volume 55 , Issue 2: Proceedings of the 21st International Radiocarbon Conference (Part 1 of 2) , 2013 , pp. 783 - 790
Copyright
Copyright © 2013 by the Arizona Board of Regents on behalf of the University of Arizona 

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References

Almenas, K, Kaliatka, A, Uspuras, E. 1998. Ignalina RBMK-1500, a Source Book [WWW document]. Lithuanian Energy Institute. ISBN 9986–492–35–1. Kaunas, Lithuania. URL: http://www.lei.lt/insc/sourcebook/.Google Scholar
Fairhall, AW, Young, JA. 1970. Radionuclides in the environment. Advances in Chemistry Series 93. Washington, DC: American Chemical Society. 402 p.Google Scholar
Hertelendi, E, Csongor, E. 1982. Anthropogenic 14C excess in the troposphere between 1951 and 1978 measured in tree rings. Radiochemical and Radioanalytical Letters 56(2): 103–10.Google Scholar
Hou, X. 2005. Rapid analysis of 14C and 3H in graphite and concrete for decommissioning of nuclear reactor. Applied Radiation and Isotopes 62(6): 871–82.CrossRefGoogle ScholarPubMed
International Atomic Energy Agency (IAEA). 2004. Management of Waste Containing Tritium and Carbon-14. Technical Report Series No. 421. Vienna: IAEA. 109 p.Google Scholar
Levin, I, Kromer, B, Barabas, M, Münnich, KO. 1988. Environmental distribution and long-term dispersion of reactor 14CO2 around two German nuclear power plants. Health Physics 54(2): 149–56.CrossRefGoogle ScholarPubMed
Libby, WF. 1946. Atmospheric helium three and radiocarbon from cosmic radiation. Physical Review 69: 671–72.CrossRefGoogle Scholar
Lithuanian Energy Institute (LEI). 2010. Nuclear Engineering Laboratory. Decommissioning project for Ignalina NPP Unit 2 final shut down and defuelling phase. Environmental Impact Assessment Report. Ignalina (LT): State Enterprise Ignalina Nuclear Power Plant (INPP); 2010 July Report No. S/14–1037.8.9/EIAR-DR1/R:5. 209 p.Google Scholar
Lukauskas, D, Plukiene, R, Plukis, A, Gudelis, A, Duskesas, G, Juodis, L, Druteikiene, R, Lujaniene, G, Luksiene, B, Remeikis, V. 2006. Method to determine the nuclide inventory of low-activity waste of the RBMK-1500 reactor. Lithuanian Journal of Physics 46(4):497–503.CrossRefGoogle Scholar
Magnusson, Å. 2007. 14C produced by nuclear power reactors - generation and characterization of gaseous, liquid and solid waste [dissertation]. Lund: Lund University. ISBN 978–91–628–7248–9. 151 p.Google Scholar
Magnusson, Å, Stenström, K. 2005. 14C produced in Swedish nuclear power reactors - measurements on spent ion exchange resins, various process water systems and ejector off-gas. Lund: Lund University, Department of Nuclear Physics; 2005 December Report No. R-05–78. 43 p.Google Scholar
Motiejunas, S, Vaidotas, A, Mazeika, J, Skuratovic, Z, Vaitkeviciene, V. 2012. Radiocarbon measurements in cemented ion-exchange resins. In: Carranza, RM, Duffo, GS, Rebak, RB, editors. Scientific Basis For Nuclear Waste Management XXXV. Proceedings of the 35th symposium of the Materials Research Society, 02–07 October 2011; Buenos Aires. Warrendale: Cambridge University Press. p 527–32.Google Scholar
National Council on Radiation Protection and Measurements (NCRP). 1985. Carbon-14 in the Environment. NCRP Report No. 81. Bethesda: NCRP. 108 p.Google Scholar
Nedveckaite, T, Motiejunas, S, Kucinskas, V, Mazeika, J, Filistovic, V, Jusciene, D, Maceika, E, Morkeliunas, L, Hamby, DM. 2000. Environmental releases of radioactivity and the incidence of thyroid disease at the Ignalina Nuclear Power Plant. Health Physics 79(6): 666–74.CrossRefGoogle ScholarPubMed
Passo, CJ Jr, Kuko, GT. 1994. Handbook of Environmental Liquid Scintillation Spectrometry. A Compilation of Theory and Methods. Meriden: Packard Instrument Company. 156 p.Google Scholar
Plukis, A, Remeikis, V, Juodis, L, Plukiene, R, Lukauskas, D, Gudelis, A. 2008. Analysis of nuclide content in Ignalina NPP. Lithuanian Journal of Physics 48(4): 375–9.Google Scholar
Raaen, FF, Ropp, GA, Raaen, HP. 1968. Carbon-14. New York: McGraw-Hill. 56 p.Google Scholar
Salonen, L, Snellman, M. 1985. Carbon-14 releases from Finnish nuclear power plants. Final Report of Research Agreement No 3065/R2/CF. Part of IAEA coordinated program on carbon-14 from nuclear power plants.Google Scholar
Veres, M, Hertelendi, E, Uchrin, G, Csaba, E, Barnabás, I, Ormai, P, Volent, G, Futó, I. 1995. Concentration of radiocarbon and its chemical forms in gaseous effluents, environmental air, nuclear waste and primary water of a pressurized water reactor power plant in Hungary. Radiocarbon 37(2):473–97.CrossRefGoogle Scholar
Yim, M-S, Caron, F. 2006. Life cycle and management of carbon-14 from nuclear power generation. Progress in Nuclear Energy 48(1):2–34.CrossRefGoogle Scholar