Spent fuel radionuclide source term model for assessing spent fuel performance in geological disposal. Part II: Matrix alteration model and global performance

Journal of Nuclear Materials

Volumn 346, Issue 1, 2005, Pages 66-77

  Poinssot, Christophe ^a   Ferry, Cécile ^a   Lovera, Patrick ^a   Jegou, Christophe ^b   Gras, Jean Marie ^c  

^a CEA SACLAY   (France)

^b DIF   (France)

^c EDF R AND D   (France)

Author keywords

[No Author keywords available]

Indexed keywords

GEOLOGICAL REPOSITORIES; HYDROGEN; MATHEMATICAL MODELS; MICROSTRUCTURE; RADIOISOTOPES; URANIUM DIOXIDE;

INSTANT RELEASE FUNCTIONS (IRF); KINETIC MODELS; LIGANDS; MATRIX ALTERATION MODEL;

SPENT FUELS;

EID: 26444600767     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2005.05.021     Document Type: Conference Paper

References (54)

1. P. Bernard, B. Barré, N. Camarcat, M. Boidron, B. Boullis, J.M. Cavedon, D. Iracane, Progress in R&D relative to high level and long-lived radioactive wastes management: Lines 1 (partitioning-transmutation) and 3 (Conditioning, long term interim storage) of the 1991 French Law, Proceedings of the Conference GLOBAL'99, Jackson Hole (USA), 29 August-3 September 1999.
2. C. Poinssot, P. Toulhoat, J.P. Piron, C. Cappelaere, L. Desgranges, J.M. Gras, Operational and Scientific questions related to the long term evolution of Spent fuel in dry conditions. Current Status of the French Research, Proceedings of the ANS Topical Meeting on Spent Nuclear Fuel Management, San Diego, 4-8 June 2000, p. 3.
3. C. Poinssot, P. Toulhoat, J.M. Gras, Long term evolution of spent nuclear fuel in long term dry storage or geological disposal. Status of the French research program PRECCI, in: Proceedings of the Global 2001 Conference, Paris, 2001.
4. C. Poinssot, P. Toulhoat, J.M. Gras, and P. Vitorge Long term evolution of spent nuclear fuel in long term storage or geological disposal. New findings from the French PRECCI R&D program and implications for the definition of the RN source term in geological repository J. Nucl. Sci. Technol. Suppl. 3 2002 473
5. L.H. Johnson, N.C. Garisto, S. Stroes-Gascoyne, Proc. Waste Management 1985, p. 479.
6. L.H. Johnson, D.F. McGinnes, Partitioning of radionuclides in Swiss power reactor fuels, Nagra Technical Report NTB 02-07, 2002.
7. E. Jacquot, S. Altmann, composition des eaux interstitielles des argillites du Callovo-Oxfordien non perturbées: état de la modélisation en Juillet 2002, ANDRA Internal Technical Report D NT ASTR 02-041, 2002.
8. M.G. Bailey, L.H. Jonhson, and D.W. Shoesmith Corr. Sci. 25 1985 233
9. S. Sunder, G.D. Boyer, and N.H. Miller J. Nucl. Mater. 175 1990 163
10. 2 dynamic leaching experiments, J. Nucl. Mater., these proceedings, doi:10.1016/j.jnucmat.2005.05.019.
11. Spent fuel disposal performance assessment (SPA projects), EU report, EUR 1935, 2000.
12. B. Grambow, A. Loida, A. Martinez-Esparza, P. Diaz-Arocas, J. de Pablo, J.L. Paul, G. Marx, J.P. Glatz, K. Lemmens, K. Ollila, H. Christensen, Long term safety of radioactive waste disposal: source term for performance assessment of spent fuel as a waste form, Forschung Zentrum Karsruhe Report, FZKA 6420, 2000.
13. L. Johnson, C. Ferry, C. Poinssot, P. Lovera, Spent fuel radionuclide source term model for assessing the spent fuel performance in geological disposal. Part I: Assessment of the Instant Release Fraction, J. Nucl. Mater., these proceedings, doi:10.1016/j.jnucmat.2005.04.071.
14. C. Poinssot, J.M. Cavedon, M. Cowper, B. Grambow, T. McMenamin, Euradwaste Conference, Luxembourg, March 2004. Proceedings available at < http://www.cordis.lu/fpb-euratom/ev_euradwaste04.htm >.
15. I. Grenthe, J. Fuger, R.J.M. Konings, R.J. Lemire, A.B. Muller, C. Nguyen Trung, and H. Wanner Nucl. Energ. Agency (OECD) 1992 715
16. J.W.T. Spinks, and R.J. Woods An introduction to radiation chemistry Third ed. 1990 Wiley Ed. New York
17. 2 matrix alteration under alpha and gamma irradiation, Nucl. Technol., in press.
18. D.W. Shoesmith J. Nucl. Mater. 282 2000 1
19. 2 containing plutonium in demineralized and carbonated water, Scientific basis for nuclear waste management XXVI Mater. Res. Soc. Symp. Proc. 757 2003 365
20. J. de Pablo, I. Casas, J. Gimenez, M. Molera, M. Rovira, L. Duro, and J. Bruno Geochim. Cosmochim. Acta 63 1999 3097
21. D.W. Shoesmith, M. Kolar, and F. King Corrosion 59 2003 802
22. H. Christensen, S. Sunder, and D.W. Shoesmith J. Alloy Compd. 213 1994 93
23. H. Christensen Nucl. Technol. 124 1998 165
24. 2 nuclear fuel matrix, Scientific basis for nuclear waste management XXVII Mater. Res. Soc. Symp. Proc. 807 2004 391
25. C. Jegou, S. Peuget, V. Broudic, D. Roudil, X. Deschanels, and J.M. Bart J. Nucl. Mater. 326 2004 144
26. D.W. Shoesmith, and J. Noil An experimental basis for a mixed potential model for nuclear fuel corrosion within a failed waste canister, Scientific basis for nuclear waste management XXVIII Mater. Res. Soc. Symp. Proc. 824 2004 81
27. G. Sattonay, C. Ardois, C. Corbel, J.F. Lucchini, M.F. Barthe, F. Garrido, and D. Gosset J. Nucl. Mater. 288 2001 11
28. C. Corbel, G. Sattonay, J.F. Lucchini, C. Ardois, M.F. Barthe, F. Huet, P. Dehaudt, B. Hickel, and C. Jegou Nucl. Instr. Meth. B 179 2001 225
29. W.J. Gray, Spent fuel dissolution rateds as a function of burnup and water chemistry, PNNL-11895, Pacific Northwest National Laboratory, 1988.
30. 2 containing alpha-emitting actinides, Radiochim. Acta 88, 527.
31. 2, Scientific basis for nuclear waste management Mater. Res. Soc. Symp. Proc. 824 2004 175
32. 2 matrix, Scientific basis for nuclear waste management XXVIII Mater. Res. Soc. Symp. Proc. 824 2004 145
33. D.W. Shoesmith J. Nucl. Mater. 282 2000 1
34. T. Eriksen, Radiolysis of water within a ruptured fuel element, SKB report PR U 96-29, 1996.
35. C. Poinssot, P. Toulhoat, J.P. Grouiller, J. Pavageau, J.P. Piron, M. Pelletier, P. Dehaudt, C. Cappelaere, R. Limon, L. Desgranges, C. Jegou, C. Corbel, S. Maillard, M.H. Fauré, J.C. Fauré, M. Masson, Synthesis on the spent nuclear fuel long-term evolution, CEA Report CEA R 5958, 2001.
36. C. Poinssot, C. Ferry, and JM. Gras Key scientific issues related to the evolution of spent nuclear fuel in long term dry storage and geological disposal, Conference Material Research Society, Scientific basis for nuclear waste management, XXVII Mater. Res. Soc. Symp. Proc. 807 2004 29
37. J.F. Ziegler, J.P. Biersack, and U. Littmark The Stopping and Range of Ions in Solids 1985 Pergamon New York
38. M. Kelm, in: Poinssot, C. et al. (Ed.), Spent Fuel Stability Under Repository Conditions-Second Annual Report, Internal CEA Report, 2003.
39. 2 in Boom clay conditions: preliminary results, Scientific basis for nuclear waste management XXVII Mater. Res. Soc. Symp. Proc. 807 2004 59
40. 2 en milieu réducteur, PhD thesis Université de Nantes, 2004.
41. S. StroessGascoyne, F. King, J.S. Betterdge, and F. Garisto Radioch. Acta 90 2002 603
42. 2 spent fuel S.E. Donnelly J.H. Evans Fundamental Aspects of Inert Gases in Solids 1991 Plenum New York
43. C. Ronchi, and J.P. Hiernaut J. Nucl. Mater. 325 2004 1
44. D. Roudil, X. Deschanels, P. Trocellier, C. Jegou, S. Peuget, and J.M. Bart Helium thermal diffusion in a uranium dioxide matrix J. Nucl. Mater. 325 2004 148
45. C. Poinssot, C. Ferry, P. Lovera, J.M. Gras, Assessment of the Commercial Spent Nuclear Fuel source terms for long term dry storage and geological disposal. Major outcomes of the French R&D Project PRECCI, American Nuclear Society Topical Meeting on Light Water Reactor Fuel Performance, Orlando, September 2004, available at < http://www.ans.fr >.
46. C. Ferry, P. Lovera, C. Poinssot, and L. Johnson Quantitative assessment of the Instant Release Fraction (IRF) for fission gases and volatile elements as a function of burnup and time under geological disposal conditions Mater. Res. Soc. Symp. Proc. 807 2004 35
47. C. Ferry, P. Lovera, C. Poinssot, P. Garcia, Enhanced diffusion under alpha self-irradiation in spent nuclear fuel: theoretical approaches, J. Nucl. Mater., these proceedings, doi:10.1016/j.jnucmat.2005.04.072.
48. P. Lovera, C. Ferry, C. Poinssot, L. Johnson, Synthesis report on the relevant diffusion coefficients of fission products and helium in spent nuclear fuel, CEA Report, CEA-R-6039, 2003.
49. C. Poinssot, C. Ferry, and P. Lovera Radionuclides release model for performance assessment studies of spent nuclear fuel in geological disposal, Scientific basis for nuclear waste management Mater. Res. Soc. Symp. Proc. 824 2004 71
50. P.A. Finn, J.K. Bates, J.C. Hoh, J.W. Emery, L.D. Hafenrichter, E.C. Buck, and M. Gong Scientific basis for nuclear waste management XVII Mater. Res. Soc. Symp. Proc. 333 1994 399
51. 2 fuel with saline brines, Forschung Zentrum Karlsruhe report FZKA 5702, 1996.
52. W. Gray, and L.E. Thomas Initial results from dissolution testing of various air-oxidised spent fuels, Scientific basis for nuclear waste management XIV Mater. Res. Soc. Symp. Proc. 333 1994 391
53. R.S. Forsyth, The SKB spent fuel corrosion program. An evaluation of results from the experimental programme performed in the Studsvik Hot cell Laboratory, SKB Technical report, TR-97-25, 1997.
54. H. Christensen, and E. Bjergbakke Studsvik KBS TR 1982 18