Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment
Source abstract
Abstract
Abstract Dissolution rates of spent UO2 fuel have been investigated using flow-through experiments under oxidizing, anoxic and reducing conditions. For oxidizing conditions, approximately congruent dissolution rates were obtained in the pH range 3–9.3 for U, Np, Ba, Tc, Cs, Sr and Rb. For these elements, steady-state conditions were obtained in the flow rate range 0.02–0.3 ml min −1 . The dissolution rates were about 3 mg d −1 m −2 for pH>6. For pH
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Radioactive element chemistry and processing · Nuclear Materials and Properties · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (40)
Show source-provided references
1. Final disposal of spent nuclear fuel. Importance of the bedrock for safety. SKB Technical Report 92-20, Swedish Nuclear Fuel and Waste Management Co., Stockholm, 1992
2. Kleykamp · Nucl. Technol. · 1988 · 80 · 41210.13182/NT88-A34065 ↗
3. Johnson · 1988
4. V.M. Oversby, Nuclear waste materials, in: R.W. Cahn, P. Haasen, E.J. Kramer (Eds.), Materials Science and Technology, in: B.R.T. Frost (Ed.), Nuclear Materials, Part 2, vol. 10 B, VCH, Weinheim, 1994
5. Werme · J. Nucl. Mater. · 1992 · 190 · 310.1016/0022-3115(92)90071-R ↗
6. Werme · J. Alloys Compounds · 1998 · 271–273 · 19410.1016/S0925-8388(98)00053-X ↗
7. Bruno · Geochim. Cosmochim. Acta · 1991 · 55 · 64710.1016/0016-7037(91)90330-8 ↗
8. Casas · Radiochim. Acta · 1994 · 66&67 · 2310.1524/ract.1994.6667.s1.23 ↗
9. J. dePablo, I. Casas, J. Gimenez, M. Molera, M.E. Torrero, in: W.J. Gray, I.R. Triay (Eds.), Scientific Basis For Nuclear Waste Management XX, Mater. Res. Soc. Symp. Proc., 465, 1997, p. 53510.1557/PROC-465-535 ↗
10. Torrero · Int. J. Chem. Kinet. · 1997 · 29 · 26110.1002/(SICI)1097-4601(1997)29:4<261::AID-KIN4>3.0.CO;2-S ↗
11. C.N. Wilson, W.J. Gray, High Level Radioactive Waste Management, vol. 2, Am. Nucl. Soc., La Grange Park, IL, 1990, p. 1431
12. High level radioactive waste management
13. dePablo · J. Nucl. Mater. · 1996 · 232 · 13810.1016/S0022-3115(96)00439-4 ↗
14. W.J. Gray, C.N. Wilson, Spent Fuel Dissolution Studies FY 1991–94, PNL-10540, UC-802, Pacific Northwest National Laboratory, Richland, Washington, 199510.2172/205055 ↗
15. W.J. Gray, Spent Fuel Dissolution Rates as a Function of Burnup and Water Chemistry, PNNL-11895, UC-802, Pacific Northwest National Laboratory, Richland, Washington, 199810.2172/671951 ↗
16. W.J. Gray, L.E. Thomas, R.E. Einziger, in: Ch.G. Interrante, R.T. Pabalan (Eds.), Scientific Basis For Nuclear Waste Management XVI, Mater. Res. Soc. Symp. Proc. 294, 1992, p. 47
17. S.A. Steward, W.J. Gray, High Level Radioactive Waste Management, American Nuclear Society, 1994, p. 2602
18. Spahiu · Radiochim. Acta · 2000 · 88 · 50710.1524/ract.2000.88.9-11.507 ↗
19. Stumm · 1996
20. K. Spahiu, L. Werme, J. Low, U.B. Eklund, in: R.W. Smith, D.W. Shoesmith (Ed.), Sci. Basis for Nuc. Waste Management XXIII, Mater. Res. Soc. Symp. Proc. 608, 2000, p. 5510.1557/PROC-608-55 ↗
21. Gran · Acta Chem. Scand. · 1950 · 4 · 55910.3891/acta.chem.scand.04-0559 ↗
22. Gran · Analyst · 1952 · 77 · 66110.1039/an9527700661 ↗
23. Eriksen · J. Nucl. Mater. · 1995 · 227 · 7610.1016/0022-3115(95)00149-2 ↗
24. J. Bruno, E. Cera, M. Grive, U.B. Eklund, T. Eriksen, Experimental determination and chemical modelling of radiolytic processes at the spent fuel/water interface, SKB Technical Report 99-26, Swedish Nuclear Fuel and Waste Management Co., Stockholm, 1999
25. D.K. Nordstrom, E.A. Jenne, J.W. Ball, in: E.A. Jenne (Ed.), Chemical Modelling in Aqueous Systems, ACS Advan. in Chem. Series 93, Am. Chem. Soc., Washington, DC, 1979, p. 5110.1021/bk-1979-0093.ch003 ↗
26. Whitfield · Limnol. Oceanogr. · 1974 · 19 · 85710.4319/lo.1974.19.5.0857 ↗
27. Nararajan · Miner. Sci. Eng. · 1974 · 6 · 35
28. R.S. Forsyth, Spent nuclear fuel corrosion: The application of ICP-MS to direct actinide analysis, SKB Technical Report 95-04, Swedish Nuclear Fuel and Waste Management Co., Stockholm, 1995
29. Garcia Alonso · J. Radioanal. Nucl. Chem. · 1996 · 203 · 1910.1007/BF02060377 ↗
30. Garcia Alonso · Radiochim. Acta · 1993 · 62 · 7110.1524/ract.1993.62.12.71 ↗
31. B. Grambow, A. Loida, P. Dressler, H.Geckeis, P. Diaz, J. Gago, I. Casas, J. dePablo, J. Gimenez, M.E. Torrero, Reaction of high burnup spent fuel in saline brines at room temperature, KFK 5377, Kernforschungszentrum Karlsruhe, Karlsruhe, 1994
32. I. Pérez Morales, PhD thesis, Universitat Politècnica de Catalunya, Barcelona, 2000
33. L. Werme, R. Forsyth, The SKB spent fuel corrosion programme. Status report 1988. SKB Technical Report 89-14, Swedish Nuclear Fuel and Waste Management Co., Stockholm, 1989
34. D. Cui, T. Eriksen, U.B. Eklund, in: Scientific Basis for Nuclear Waste Management, Sydney, 2000, Mater. Res. Soc. Symp. Proc. (2001) (accepted for publication)
35. S. Röllin, U.B. Eklund, K. Spahiu, Radiochim. Acta (accepted for publication)
36. R. Forsyth, The SKB spent fuel corrosion programme, An evaluation of results from the experimental programme performed in the Studsvik Hot Cell Laboratory, SKB Technical Report 97-25, Swedish Nuclear Fuel and Waste Management Co., Stockholm, 1997
37. Grandstaff · Econ. Geol. · 1976 · 71 · 149310.2113/gsecongeo.71.8.1493 ↗
38. V.M. Oversby, Uranium dioxide, SIMFUEL, and spent fuel dissolution rates – a review of published data, SKB Technical Report 99-22, Swedish Nuclear Fuel and Waste Management Co., Stockholm, 1999
39. K. Spahiu, P. Sellin, in: Scientific Basis for Nuclear Waste Management XXIV, Sydney, 2000, Mater. Res. Soc. Symp. Proc. (2001) (accepted for publication)
40. Röllin · J. Chromatogr. A · 2000 · 884 · 13110.1016/S0021-9673(99)01319-9 ↗