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BY-NC-ND 3.0 license Open Access Published by De Gruyter Open Access November 26, 2014

Preliminary evaluation of 14C and 36Cl in nuclear waste from Ignalina Nuclear Power Plant decommissioning

  • Jonas Mažeika EMAIL logo , Galina Lujanienė , Rimantas Petrošius , Nadežda Oryšaka and Sergej Ovčinikov
From the journal Open Chemistry

Abstract

On a first attempt, the determination of 14C and 36Cl activity concentrations in basic operational waste (spent ion-exchange resins and perlite mixture), in decommissioning waste (construction concrete, sand, stainless steel and serpentinite) and irradiated graphite from the Ignalina NPP has been performed. The samples for measurement of the specific activity of 14C and 36Cl were obtained from the selected places, where the highest values of the dose rate and the activity concentrations of gamma emitters were found. The performed study of the total 14C and 36Cl activity concentrations was based on estimated chemical forms of 14C (inorganic and organic compounds) and 36Cl as Cl- ion. The tested methods used in this study were found to be suitable for estimation of activity concentrations of measured radionuclides.

References

[1] Almenas K., Kaliatka A., Uspuras E., Ignalina RBMK-1500, Lithuanian Energy Institute, Kaunas, 1998, http://www.lei.lt/insc/sourcebook/ Search in Google Scholar

[2] Lukauskas D., Plukiene R., Plukis A., Gudelis A., Duskesas G., Juodis L., et al., Lith. J. Phys., 2006, 46, 497 Search in Google Scholar

[3] Plukis A., Remeikis V., Juodis L., Plukiene R., Lukauskas D., Gudelis A., Lith. J. Phys., 2008, 48, 375 Search in Google Scholar

[4] Ancius D., Ridikas D., Remeikis V., Plukis A., Plukiene R., Cometto M., Nukleonika, 2004, 50, 113 Search in Google Scholar

[5] Huskisson N.S., Ward P.F.V., Int. J. Appl. Radiat. Isot., 1978, 29, 729 10.1016/0020-708X(78)90120-5Search in Google Scholar

[6] Wenzel U., Herz D., Schmidt P., J. Radioanal. Chem., 1979, 53, 7 10.1007/BF02517901Search in Google Scholar

[7] Salonen L., Snellman M., 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, IAEA, Vienna, 1985 Search in Google Scholar

[8] Martin J.E., Health Phys., 1986, 50(1), 57 10.1097/00004032-198601000-00004Search in Google Scholar PubMed

[9] Veres M., Hertelendi E., Uchrin G., Csaba E., Barnabás I., Ormai P., et al., Radiocarbon, 1995, 37, 473 10.1017/S0033822200030976Search in Google Scholar

[10] Yang H.Y., Wang Z.H., Liu W., Wen X.L., Zheng H., Chin. J. Atomic Energy Sci. Technol., 1996, 30(6), 509 Search in Google Scholar

[11] Wickenden D.A., Environmental Radiochemical Analysis, Royal Society of Chemistry (Special Publication), 1999, 234, 170 Search in Google Scholar

[12] Hou X., Appl. Rad. Isot., 2005, 62, 871 10.1016/j.apradiso.2005.01.008Search in Google Scholar PubMed

[13] Magnusson Å., 14C produced by nuclear power reactors – generation and characterization of gaseous, liquid and solid waste, PhD thesis, Lund, Lund University, 2007 Search in Google Scholar

[14] Hou X., J. Radioanal. Nucl. Chem. 2007, 273, 43 10.1007/s10967-007-0708-xSearch in Google Scholar

[15] Magnusson Å., Aronsson P.O., Lundgren K., Stenström K., Health Phys., 2008, 95(2), 110 10.1097/01.HP.0000309765.35223.14Search in Google Scholar PubMed

[16] Itoh M., Watanabe K., Hatakeyama M., Tachibana M., Analyst, 2002, 127(7), 964 10.1039/b200250gSearch in Google Scholar PubMed

[17] Rodriguez M., Pina G., Lara E., Czechoslov. J. Phys., 2006, 56, D211 10.1007/s10582-006-0507-6Search in Google Scholar

[18] Hou X., Østergaard L.F., Nielsen S.P., Anal. Chem., 2007, 79, 3126 10.1021/ac070100oSearch in Google Scholar PubMed

[19] Zulauf A., Happel S., Mokili M.B., Bombard A., Jungclas H., J. Radioanal. Nucl. Chem., 2010, 286(2), 539 10.1007/s10967-010-0772-5Search in Google Scholar

[20] Fifield L.K., Tims S.G., Stone J.O., Argento D.C., De Cesare M., Nucl. Instr. Meth. Phys. Res. B, 2013, 294, 126 10.1016/j.nimb.2012.04.028Search in Google Scholar

[21] IAEA. Management of waste containing tritium and carbon-14, Technical Report Series No. 421, IAEA, Vienna, Austria, 2004 Search in Google Scholar

[22] IAEA. Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors, IAEA-TECDOC-1521, IAEA, Vienna, Austria, 2006 Search in Google Scholar

[23] Bushuev A.V., Zubarev V.N., Proshin I.M., Atomnaya energija, 2002, 92, 298 (in Russian) 10.1023/A:1016506110872Search in Google Scholar

[24] Yim M.-S., F. Progress in Nuclear Energy, 2006, 48, 2 10.1016/j.pnucene.2005.04.002Search in Google Scholar

[25] Metcalfe M.P., Banford A.W., Eccles H., Norris S., J. Nucl. Materials, 2013, 436, 158 10.1016/j.jnucmat.2012.11.016Search in Google Scholar

[26] Mughabghab S.F., Divadeenam M., Holden N.E., Neutron Cross Sections from Neutron Resonance Parameters and Thermal Cross Sections, Academic Press, New York, 1981 10.1016/B978-0-12-509701-7.50007-9Search in Google Scholar

[27] Vaitkevičienė V., Mažeika J., Skuratovič Ž., Motiejūnas S., Vaidotas A., Oryšaka A., Ovčinikov S., Radiocarbon, 2013, 55, 783 10.1017/S0033822200057945Search in Google Scholar

Received: 2014-2-28
Accepted: 2014-6-16
Published Online: 2014-11-26

© 2015 Jonas Mažeika et al.

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

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