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Solubility and Colloid Generation of Plutonium from Leaching of a HLW Glass in Salt Solutions

Published online by Cambridge University Press:  26 February 2011

J. I. Kim ,
W. Treiber ,
Ch. Lierse  and
P. Offermann
J. I. Kim
Affiliation:
Institut für Radiochemie, TU München, 8046 Garching, FRG
W. Treiber
Affiliation:
Institut für Radiochemie, TU München, 8046 Garching, FRG
Ch. Lierse
Affiliation:
Institut für Radiochemie, TU München, 8046 Garching, FRG
P. Offermann
Affiliation:
Hahn-Meitner Institut für Kernforschung, 1000 Berlin, FRG
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Abstract

Solubilities of Pu from leaching of a simulated HLW glass (C31–3-EC) spiked with 5 wt % Pu and from PuO2 are determined in salt solutions of different NaCl concentration and in groundwaters which are representative for the Gorleben area. Th.e leaching experiment is carried out either in an autoclave at 200 °C or under normal conditions (1 atm, 25°C). Solubilities of Pu in all investigated solutions are observed to be considerably higher than the values known from theoretical estimates. The predominant Pu species in solutions are found to be microcolloids, which are characterized by means of ultrafiltration and pulsed laser-induced photoacoustic spectroscopy.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 359
Copyright
Copyright © Materials Research Society 1985

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References

1. Engelmann, Ch., Ed., Joint Annual Progress Report to the CEC Action No. 5, EUR 9268 EN, (1982)Google Scholar
2. Lutze, W., Ed., “Scientific Basis for Nuclear Waste Management V”, MRS Symp. Proc. Vol.16, North-Holland, New York (1982)Google Scholar
3. McVay, G. L., Ed., “Scientific Basis for Nuclear Waste Management VII”, MRS Symp. Proc. Vol.26, North-Holland, New York (1984)Google Scholar
4. Kim, J. I., Apostolidis, Ch., Buckau, G. and Ch. Lierse, Progress Report to the CEC Mirage Project, RCM 01484, TU Munich (1984)Google Scholar
5. Pickering, S., Walker, C. T. and Offermann, P., in Ref. 2, pp 113–124 Google Scholar
6. “Nuclear Waste Material Handbook”, Material Characterization Center, DOE/TIC -11400, PNL, Richland (1981)Google Scholar
7. Stumpe, R., Kim, J. I., Schrepp, W. and Walther, H., Appl. Phys. B 34, 203 (1984)Google Scholar
8. Schrepp, W., Stumpe, R., Kim, J. I. and Walther, H., Appl. Phys. B 32, 207 (1983)Google Scholar
9. Rai, D., Strickert, R. G. and Ryan, J. L., J. Inorg. Nucl. Chem. Lett., 16, 551 (1981)CrossRefGoogle Scholar
10. Kim, J. I., Lierse, Ch. and Baumgärtner, F., in “Plutonium Chemistry”, Eds. Carnall, W. T. and Choppin, G. R., ACS Symp. Ser. 216 American Chemical Society, Washington D. C., (1983) pp 317–334 Google Scholar
11. Büppelmann, K., Diplom-Thesis, Technical University Munich (1984)Google Scholar
12. Moon, Ch., Lierse, Ch. and Kim, J. I., in preparationGoogle Scholar
13. Kim, J. I., Buckau, G., Baumgartner, F., Moon, H. C. and Lux, D., in Ref. 3, pp 31–40 Google Scholar
14. Kim, J. I., Bernkopf, M., Buckau, G., Lierse, Ch., Lux, D. and Rommel, H., Progress Report to the German Migration Project, PTB-Braunschweig, RCM 02984, TU Munich (1984)Google Scholar
15. Nitsche, H., Private communicationGoogle Scholar
16. Costanzo, D. A., Biggers, R. E. and Bell, J. T., J. Inorg. Nucl. Chem., 35, 609 (1973)Google Scholar