Long term modelling of spent fuel oxidation/dissolution under repository conditions

Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM

Volumn 2, Issue , 2001, Pages 729-734

  Merino, Juan ^a   Cera, Esther ^a   Bruno, Jordi ^a   Eriksen, Trygve ^b   Quiñones, Javier ^c   Martínez Esparza, Aurora ^a  

^a QuantiSci SL ^*  (Spain)

^b ROYAL INSTITUTE OF TECHNOLOGY   (Sweden)

^c CIEMAT   (Spain)

Author keywords

[No Author keywords available]

Indexed keywords

ALPHA PARTICLES; CODES (SYMBOLS); DIFFERENTIAL EQUATIONS; DISSOLUTION; IRRADIATION; MASS TRANSFER; MATHEMATICAL MODELS; RADIOACTIVE WASTE STORAGE; RADIOISOTOPES; RADIOLYSIS; REDOX REACTIONS; SOLUBILITY; SPENT FUELS; THERMODYNAMICS; URANIUM DIOXIDE;

DYNAMIC REDOX SYSTEMS; RADIOACTIVE DECAY;

RADIOACTIVE WASTE DISPOSAL;

EID: 0346961137     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (22)

1. BRUNO J., CERA E., DURO L., ERIKSEN T.E. and WERME L.O., 1996. A kinetic model for the stability of spent fuel matrix under oxic conditions. J. Nucl. Mater. 238, 110-120.
2. BRUNO J., CERA E., DURO L., ERIKSEN T.E. SELLIN P. SPAHIU K. and WERME L.O., 1997b. A kinetic model for the stability of the spent fuel matrix under oxic conditions. Model development against experimental evidence. Mat. Res. Soc. Symp. Proc. 465, 491-502.
3. 2 spent nuclear fuel. Application of the model to the minor radionuclides. SKB Technical Report. TR-98-22.
4. ERIKSEN T.E., EKLUND U.-B., WERME L.O. and BRUNO J., 1995. Dissolution of irradiated fuel: a radiolytic mass balance study. J. Nucl. Mater. 227, 76-82.
5. BRUNO J., CERA E., GRIVÉ M., EKLUND U.-B. and ERIKSEN T.E., 1999. Experimental determination and chemical modelling of radiolytic processes at the spent fuel/water interface. SKB Technical Report. TR-99-26
6. CERA E., MERINO J. and BRUNO J., 2000. Liberación de los radionucleidos e isótopos estables contenidos en la matriz del combustible. Modelo conceptual y modelo matemático del comportamiento del residuo. Publicación Técnica ENRESA 3/2000.
7. QUIÑONES, J., SERRANO, J., DÍAZ AROCAS, P., RODRÍGUEZ ALMAZÁN, J.L., BRUNO, J., CERA, E., MERINO, J., ESTEBAN, J.A., MARTÍNEZ-ESPARZA, A., 2000. Cálcule de la generación de productos radiolíticos en agua por radiación α. Determinación de la velocidad de alteración de la matriz del combustible nuclear gastado. Publicación Técnica ENRESA 2/2000.
8. th International Symposium on Nuclear Waste Management. Sydney, August 27-31 2000.
9. FONT I., pers. comm.
10. ARCOS D., BRUNO J., DURO L., GRIVÉ M., 2000. Desarrollo de un modelo geoquímico de campo próximo. Pubicación Técnica ENRESA 4/2000.
11. WOLERY T.J., 1992. EQ3NR, A Computer Program for Geochemical Aqueous Speciation-Solubility Calculations: Theoretical Manual, User's Guide, and Related Documentation (Vesrsion 7.0). UCRL-MA-110662 PT III, Lawrence Livermore National Laboratory, Livermore, California.
12. AMBER, 1999. AMBER 4.0 Reference Guide. QSL-5046a-1 Version 1.0 Oct 1998 Enviros Software Solutions. AMBER 4.2 Release Note. QSL-5046A-4 Version 1.0 Nov 1999 QuantiSci Limited. Henley-on-Thames, UK.
13. KIRKEGAARD, P. and BJERGBAKKE, E., 2000. CHEMSIMUL: A simulator for chemical kinetics. Risø-R-1085(EN).
14. RODRIGUEZ ALMAZÁN J.L., DÍAZ P., SERRANO J., COBOS J., QUIÑONES J., CUÑADO M.A., ESTEBA J.A., 1998. Estimación de la generación de gases y otros productos radiolíticos en el agua del campo próximo en un almacén geológico profundo, a partir del cálcule de la tasa de dosis alfa (α) y gamma (γ). Ciemat DFN/RA-1/SP98.
15. ERIKSEN T.E., CHRISTENSEN H., BJERGBAKKE E., 1987. Journal of Radioanalytical and Nuclear Chemistry, 116, 13-25.
16. CHRISTENSEN H., SUNDER S., 1998. Current state of knowledge in radiolysis effects on spent fuel corrosion. STUDSVIK/M-98/71.
17. WERME, L.O., GRAMBOW, G., 1987. Development, Application and Validation of Models for Waste Package Long-Term Performance; Current Trends. Mat. Res. Soc. Symp. Proc. 84, 29-44.
18. GRAMBOW, B., LOIDA, A., MARTÍNEZ-ESPARZA, A., DÍAZ-AROCAS, P., DE PABLO, J., PUAL, J.-L., MARX, G., GLATZ, J.-P., LEMMENS, K., OLLILA, K., CHRISTENSEN, H., 2000. Source term for performance assessment of spent fuel as a waste form. Contract FI4W-CT95-0004, European Comission, EUR 19140.
19. SR 97, 1999. Post-closure safety. Main Report, Volume II SKB.
20. ERIKSEN T., 1996. Radiolysis of water within a ruptured fuel element. PR U-96-29. SKB.
21. th International Conference on the Chemistry and Migration Behaviour of Actinides and Fission Products in the Geosphere. Bregenz, Austria, September 16-21, 2001.
22. Evaluated Nuclear Structure Data File (ENSDF), National Nuclear Data Center, Brookhaven National Laboratory. http://www.nndc.bnl.gov/nndc/ensdf/