Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor

Radiochimica Acta

Volumn 97, Issue 9, 2009, Pages 491-496

  Serrano Purroy, D ^a   Clarens, F ^b   J P Glatz, ^a   Wegen, D ^a   Christiansen, B ^a   De Pablo, J ^b,c   Gimenez, J ^c   Casas, I ^c   Martinez Esparza A ^d  

^a JOINT RESEARCH CENTRE   (Italy)

^b FUNDACIÓ CTM CENTRE TECNOLÒGIC   (Spain)

^c UNIVERSITAT POLITÈCNICA DE CATALUNYA   (Spain)

^d Empresa Nacional de Residuos Radiactivos SA   (Spain)

Author keywords

Commercial spent fuel; Dissolution rate; Dynamic leaching

Indexed keywords

EID: 70350161672     PISSN: 00338230     EISSN: None     Source Type: Journal    
DOI: 10.1524/ract.2009.1640     Document Type: Article

References (42)

1. Johnson, L. H., Shoesmith, D. W.: Radioactive Waste Forms for the Future. (Lutze, W., Ewing, R. C, eds.) Elsevier, Amsterdam (1988).
2. Shoesmith, D. W.: J. Nucl. Mater. 282, 1-31 (2000).
3. Bruno, J., Ewing, R. C: Elements 2, 343-349 (2006).
4. Rollin, S., Spahiu, K., Eklund, U.-B.: J. Nucl. Mater. 297, 231-243 (2001).
5. Gray, W. J., Strachan, D. M.: Mater. Res. Soc. Symp. Proc. 212, 205-212(1991).
6. Gray, W. J., Wilson, C. N.: Spent fuel dissolution studies. FY 1991 to 1994. Pacific Northwest Laboratory Report PNL-10540, Richland, USA (1995).
7. Gray, W. J., Leider, H. R., Steward, S. A.: J. Nucl. Mater. 190,46-52 (1992).
8. Giménez, J., Casas, I., de Pablo, J., Martínez-Esparza, A.: Secondary-phase formation on U02 fuel. Deliverable 1.5.8, NF-PRO Project (2005).
9. Wilson, C. N.: Summary of results from the series 2 and series 3 NNWSI bare fuel dissolution tests. Mater. Res. Soc. Symp. Proc. 112, 473-483 (1988).
10. Wilson, C. N.: Results from NNWSI Series 3 spent fuel dissolution tests. Pacific Northwest Laboratory Report PNL-7170, June 1990. Richland, Washington, USA (1990).
11. Wilson, C. N.: Results from NNWSI Series 2 bare fuel dissolution tests. Pacific Northwest Laboratory Report PNL-7169, September 1990. Richland, Washington, USA (1990).
12. Sunder, S., Miller, N. H.: Oxidation of CANDU uranium oxide fuel by air in gamma radiation at 150 °C. J. Nucl. Mater. 231, 121-131 (1996).
13. Forsyth, R. S., Werme, L. O.: Spent fuel corrosion and dissolution. J. Nucl. Mater. 190, 3-19 (1992).
14. Stroes-Gascoyne, S., Johnson, L. H., Tait, J. C., McConnell, J. L., Porth, R. J.: Leaching of used CANDU fuel: results from a 19-year leach test under oxidizing conditions. Mater. Res. Soc. Symp. Proc. 465, 511-518 (1997).
15. Finn, P. A., Finch, R. J., Buck, E. C, Bates, J. K.: Corrosion mechanisms of spent fuel under oxidizing conditions. Mater. Res. Soc. Symp. Proc. 506, 123-131(1998).
16. Finch, R. J., Buck, E. C, Finn, P. A., Bates, J. K.: Oxidative corrosion of spent UO2 fuel in vapor and dripping groundwater at 90 °C. Mater. Res. Soc. Symp. Proc. 556,431-438 (1999).
17. McNamara, B., Buck, E., Hanson, B.: Observation of studtite and metastudtite on spent fuel. Mater. Res. Soc. Symp. Proc. 757, 401-406(2003).
18. Haschke, J. M., Oversby, V. M.: J. Nucl. Mater. 305, 187-201 (2002).
19. Bruno, J., Casas, I., Puigdomènech, I.: Geochim. Cosmochim. Acta 55, 647-658(1991).
20. Casas, I., Giménez, J., Martí, V., Torrero, M. E., de Pablo, J.: Radiochim. Acta 66/67. 23-27 (1994).
21. Developed at the University of Texas Health Science Center at San Antonio, Texas and available from the Internet by anonymous FTP from maxrad6.uthscsa.edu.
22. Johnson, L., Ferry, C, Poinssot, Ch., Lovera, P.: J. Nucl. Mater. 346 56-65 (2005).
23. Loida, A., Grambow, B., Geckeis, H.: J. Nucl. Mater. 238, 11-22 (1996).
24. Serrano, J. A., Glatz, J. P., Toscano, E. H., Barrero, J., Papaioannou, D.: J. Nucl. Mater. 294, 339-343 (2001).
25. Serrano, J. A., Glatz, J. P., Toscano, E. H., Papaioannou, D., Barrero, J., Coquerelle.M.: J. Alloys Compd. 271-273, 573-576 (1998).
26. Gray, W. J., Thomas, L. E., Einziger, R. E.: Effects of air oxidation on the dissolution rate of LWR spent fuel. Mater. Res. Soc. Symp. Proc. 294, 47-54(1983).
27. Burns, P. C: J. Nucl. Mater. 265 218-223 (1999).
28. Hoskin, P. W. O., Burns, P. C: Mineral. Mag. 67 689-696 (2003).
29. Douglas, M., Clark, S. B., Utsunomiya, S., Ewing, R. C: J. Nucl. Sci. Technol. Suppl. 3, 504-507 (2002).
30. Giménez, J., Rovira, M., de Pablo, J., Casas, I., Martínez-Esparza, A., Martínez-Lladó, X.: Sorption of caesium on freshly precipitated studtite (UO4-4H2O). Sorption kinetics and isotherms. Presented at the International Workshop on Mobile Fission and Activation Products in Nuclear Waste Disposal. La Baule, France (2007).
31. Finn, P. A., Hoh, J. C, Wolf, S. F., Slater, S. A., Bates, J. K.: Radiochim. Acta 74, 65-71 (1996).
32. Jégou, C, Peuget, S., Broudic, V., Roudil, D., Deschanels, X., Bart, J. M.: J. Nucl. Mater. 326, 144-155 (2004).
33. Werme, L. O., Spahiu, K.: J. Alloys Compd. 271-273, 194-200 (1998).
34. Hanson, B., Stout, R.: Mat. Res. Symp. Proc. 824, 89-91 (2004).
35. Gray, W. J.: Comparison of uranium release from spent fuel and unirradiated UO2 in salt brine. Mater. Res. Soc. Symp. Proc. 84, 141-152(1987).
36. Neck, V., Altmaier, M., Seibert, A., Yun, J. L., Marquardt, C. M., Fanghänel.Th.: Radiochim. Acta 95, 193-207 (2007).
37. Neck, V., Altmaier, M., Fanghänel, Th.: C.R. Chim. 1-19 (2007).
38. Burns, P. C, Ewing, R. C, Miller, M. L.: J. Nucl. Mater. 245, 1-9 (1997).
39. Burns, P. C, Deely, K. M., Skanthakumar, S.: Radiochim. Acta 92, 151-159 (2004).
40. Friese, J. I., Douglas, M., McNamara, B. K., Clark, S. B., Hanson, B. D.: Np behaviour in synthesized uranyl phases: results of initial tests. Pacific Northwest National Laboratory Report, PNNL-14856, USA (2004).
41. Douglas, M., Clark, S. B., Friese, J. I., Arey, B. W, Buck, E. C, Hanson, B. D.: Environ. Sci. Technol. 39, 4117-4124 (2005).
42. Buck, E. C, Finch, R. J., Finn, P. A., Bates, J. K.: Retention of neptunium in uranyl alteration phases formed during spent nuclear fuel corrosion. Mater. Res. Soc. Symp. Proc. 506, 87-94 (1998).