Partition characteristics of radionuclides during a melt decontamination of a contaminated metal waste

Byeong-Yeon Min; Wang-Kyu Choi; Won-Zin Oh; Chong-Hun Jung; Kune-Woo Lee

Journal of Industrial and Engineering Chemistry, Vol.15, No.1, 31-35, January, 2009

DOI10.1016/j.jiec.2008.08.015 Export Citation

Partition characteristics of radionuclides during a melt decontamination of a contaminated metal waste

Byeong-Yeon Min, Wang-Kyu Choi^†, Won-Zin Oh , Chong-Hun Jung, and Kune-Woo Lee

Korea Atomic Energy Research Institute, P.O. Box 150, Yusung-Gu, Daejeon 305-600, Republic of Korea

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Melt decontamination of radioactive contaminated metal waste using arc melting process is investigated the characteristic behavior phenomena of radioisotope cobalt-60 (60Co) and cesium-137 (137Cs) from a molten ingot, slag and dust for the effect of the basicity and various slag types. The composition of the slag former used to capture the contaminants (60Co, 137Cs) during the melt decontamination process generally consisted of silica (SiO2), calcium oxide (CaO) and aluminum oxide (Al2O3). Also, calcium fluoride (CaF2), magnesium oxide (MgO), and ferric oxide (Fe2O3) were added to provide an increase in the slag fluidity and oxidative potential. More 60Co was transfer to the slag phase in the carbon steel than the stainless steel. Most of the 60Co remained in the ingot phase at about above 90% present. 60Co was removed from the ingot phase to slag phase by up to 12% at about 0.8 of the slag basicity in carbon steel. There was found that significant amounts of 60Co remain in the ferric oxide slag at up to 32%. Flux containing CaF2 was significantly captured to the slag phase by up to 30%. In all the tests, 137Cs was completely eliminated from the melt of the stainless steel as well as the carbon steel and distributed to the slag and dust phase. In the slag basicity at 0.5, a maximum of 25% of the 60Cs remained in the slag phase to the carbon steel. Fluoride slags favor a capture of cesium in the slag. A maximum of 30% of the 137Cs remained in a ferric oxide slag.

Keywords:Melting decontamination;Slag;Ingot;Partitioning;Radionuclide

[References]

Choi WK, Song PS, Min BY, Kim HI, Jung CH, Oh WZ, KAERI/AR-716/2004, Korea Atomic Energy Research Institute, 2004
Soleimani M, Kaghazchi T, J. Ind. Eng. Chem., 14(1), 28 (2008)
Hamm M, Kreh R, Quade U, Safewaste, 2000, 995 (2000)
Adams V, Murphie W, Gresalfi M, Safewaste, 2000, 115 (2000)
Hopkinson KL, Bishop A, Cross MT, Harrison J, Selgas, Nuclear safety and the environment, European Commission, EUR 18041 EN, 1998 (1998)
Harvey DS, EUR 12605, European Communities (1990)
Grabener KH, Beyer H, Westermann H, European Commission, Krefeld, Germany, 1993, p. 209
Worcester SA, Twidwell LG, Paolini DJ, Meldon TA, Mizia RE, WINCO-1198, Westinghouse Idaho Nuclear Company, Idaho Falls, Idaho (1994)
Buckentin JM, Damkroger BK, Schlienger ME, SAND 96-0902 (1996)
Park HS, Kim SJ, J. Ind. Eng. Chem., 11(5), 657 (2005)
Joanna MB, Brian KD, Eric Schlinenger M, SAND 96-0902, Category UC-704 (1998)
Gomer CR, Lambley JT, EUR-10188, Commission of European Communities (1985)
Worcester SA, Twidwell LG, Paolini DJ, Weldon TA, Mizia RE, WINCO-1138 (1993)
Sappok M, Decommissioning of Nuclear Installations, Elsevier Applied Science, 1990,, p. 482
Nakamura H, Fujiki K, Radioactive Metal Melting Test at Japan, Atomic Energy Research Institute (1993)
Larsen M, EGG-2411 EG&G Idaho, Inc. (1985)
Larsen M, PG-Am-85-005. Idaho National Engineering Laboratory, EG&G Idaho, Inc., (1985)
Turkdogan ET, Physical Chemistry of High Temperature Technology, vol. 140, Academic Press, New York (1980)
Kellog HH, Trans. Met. Soc. AIME, 236, 602 (1966)
Buckley M, Handy B, Hillis ZK, NCC Limited, 11426/TR/0001 (2004)

[Referenced By]

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[1] Choi WK, Song PS, Min BY, Kim HI, Jung CH, Oh WZ, KAERI/AR-716/2004, Korea Atomic Energy Research Institute, 2004

[2] Soleimani M, Kaghazchi T, J. Ind. Eng. Chem., 14(1), 28 (2008)

[3] Hamm M, Kreh R, Quade U, Safewaste, 2000, 995 (2000)

[4] Adams V, Murphie W, Gresalfi M, Safewaste, 2000, 115 (2000)

[5] Hopkinson KL, Bishop A, Cross MT, Harrison J, Selgas, Nuclear safety and the environment, European Commission, EUR 18041 EN, 1998 (1998)

[6] Harvey DS, EUR 12605, European Communities (1990)

[7] Grabener KH, Beyer H, Westermann H, European Commission, Krefeld, Germany, 1993, p. 209

[8] Worcester SA, Twidwell LG, Paolini DJ, Meldon TA, Mizia RE, WINCO-1198, Westinghouse Idaho Nuclear Company, Idaho Falls, Idaho (1994)

[9] Buckentin JM, Damkroger BK, Schlienger ME, SAND 96-0902 (1996)

[10] Park HS, Kim SJ, J. Ind. Eng. Chem., 11(5), 657 (2005)

[11] Joanna MB, Brian KD, Eric Schlinenger M, SAND 96-0902, Category UC-704 (1998)

[12] Gomer CR, Lambley JT, EUR-10188, Commission of European Communities (1985)

[13] Worcester SA, Twidwell LG, Paolini DJ, Weldon TA, Mizia RE, WINCO-1138 (1993)

[14] Sappok M, Decommissioning of Nuclear Installations, Elsevier Applied Science, 1990,, p. 482

[15] Nakamura H, Fujiki K, Radioactive Metal Melting Test at Japan, Atomic Energy Research Institute (1993)

[16] Larsen M, EGG-2411 EG&G Idaho, Inc. (1985)

[17] Larsen M, PG-Am-85-005. Idaho National Engineering Laboratory, EG&G Idaho, Inc., (1985)

[18] Turkdogan ET, Physical Chemistry of High Temperature Technology, vol. 140, Academic Press, New York (1980)

[19] Kellog HH, Trans. Met. Soc. AIME, 236, 602 (1966)

[20] Buckley M, Handy B, Hillis ZK, NCC Limited, 11426/TR/0001 (2004)