Skip to main content Accessibility help
×
Home

The Fate of Radiogenic Iodine During the Electrochemical Treatment of Spent EBR-II Fuel

  • Steven Frank (a1), DeeEarl Vaden (a2), Brian R Westphal (a3), Thomas A Johnson (a4), Paula A Hahn (a5), Jeff J. Giglio (a6), Daniel G. Cummings (a7) and Michael Rodriquez (a8)...

Abstract

Radiogenic iodine is one of the more difficult fission products to capture and immobilize during the reprocessing of spent nuclear fuel.

However, for metallic fuels reprocessed by electrometallurgical treatment, it is believed that the majority of fission-product iodine is retained during the various processing steps. Spent fuel from the Experimental Breeder Reactor II (EBR-II) at the Idaho National Laboratory (INL) is being treated by a combination of electrochemical and pyrometallurgical methods to deactivate the bond sodium of the fuel, recover uranium, and immobilize fission products for disposal. This paper discusses the progress of various strategies and experiments to confirm the expected retention of iodine during the electrometallurgical treatment of EBR-II spent fuel. This includes surveys of previous observations and measurements, and the direct measurement of iodine from various process samples. Current measurements are aimed at iodine determination in the bond sodium and plenum regions of the fuel, refined iodine measurements in electrorefiner salt, and the retention of iodine during waste form production.

Copyright

References

Hide All
1 Moran, J.E., Oktay, S.D., Santschi, P.H., and Schink, D.R., Environ. Sci. Tech. 33, 25362542 (1999).
2 Raisbeck, G.M., Yiou, F., Zhou, Z.Q., and Kilius, L.R., J. Marine Systems 6, 561570 (1995).
3 National Research Council, “Electrometallurgical Techniques for DOE Spent Fuel Treatment: Final Report,” National Academy Press, Washington, DC (2000).
4 Goff, K.M., Benedict, R.W., Johnson, S.G., Mariani, R.D., Simpson, M.F., Westphal, B.R., “Electrometallurgical Treatment Denonstration at ANL-West,” Proceedings of the ANS Embedded Topical Meeting DOE Spent Nuclear Fuel and Fissile Material Management (2000).
5 McDeavitt, S.M., Abraham, D.P., Park, J.Y., and Keiser, D.D. Jr., JOM, 49 (7), 29 (1997).
6 Simpson, M.F., Goff, K.M., Johnson, S.G., Bateman, K.J., Battisti, T.J., Toews, K.L., Frank, S.M., Moschetti, T.L., and O'Holleran, T.P., Nuc. Tech., 134, 263 (2001).
7 Schuster, E., Garzarolli, F., Kersting, A., Neeb, K.H., and Stehle, H., Nuclear Engineering and Design, 64, 8185 (1981).
8 Chellew, N.R., Honesty, C.C., and Steunenberg, R.K., “Laboratory Studies of Iodine Behavior in EBR-II Melt Refining Process,” Report ANL-6815, Argonne National Laboratory, 1964.
9 Castleman, A.W. Jr. , Tang, I.N., J. inorg. Nucl. Chem, 32, 1057 to 1064, 1970.
10 Castleman, A.W. Jr., Nuclear Safety, 11, No 5, 379 (1970).
11 Erdman, C.A., Kelly, J.L., and Reynolds, A.B., Nuclear Safety, 16, No. 3, 318 (1975).
12 Bruchertseifer, H., Cripps, R., and Jaeckel, B., Anal. Bioanal. Chem., 375, 1107 (2003).
13 McKnight, R.D., “ANL Calculational Methodologies for Determining Spent Nuclear Fuel Source Term,” International Conference on the Physics of Nuclear Science and Technology, Long Island, NY, USA (1998).
14 Vaden, D., Separation Science and Technology, 41, (10), 1985 (2006).
15 Lewis, M.A., Hash, M.C., Hebden, A.S., and Ebert, W.L., “Tests with Ceramic Waste Form Materials Made by Pressureless Consolidation,” Argonne National Laboratory Report ANL-02/10 (2002).
16 Choi, B.S., Park, G.I., Kim, J.H., Lee, J.W., and Begg, B.D., J. Nucl. Mat., 341, 93 (2001).

Keywords

Metrics

Full text views

Total number of HTML views: 0
Total number of PDF views: 0 *
Loading metrics...

Abstract views

Total abstract views: 0 *
Loading metrics...

* Views captured on Cambridge Core between <date>. This data will be updated every 24 hours.

Usage data cannot currently be displayed