Hostname: page-component-7bb8b95d7b-495rp Total loading time: 0 Render date: 2024-10-04T08:15:33.345Z Has data issue: false hasContentIssue false

Modeling of Geochemical Compatibility of Near Field Materials in Terms of Radionuclide Retention Properties

Published online by Cambridge University Press:  20 August 2019

P. L. Lucille
Affiliation:
Electricité de France, Research and Development Division
A Burnol
Affiliation:
Laboratoire National d'Hydraulique, Chatou, France
Ph. Ollar
Affiliation:
Département Etudes de Matériaux, Moret sur Loing, France
Get access

Abstract

The containment of radionuclides over very long periods of time is based on the interposition of a multi-barrier system between the waste and the biosphere. A performance allocation study is usually conducted for each barrier. Each barrier is then designed, in terms of geometry and composition, to cope with the performance it has been allocated. However geochemical interactions will occur between the different barriers. An alkaline plume will be generated by cement materials, a redox front will be generated by container corrosion and geochemical gradients will be generated by the dissolution of artificial barriers by natural groundwater. Radionuclide retention mechanisms are strongly pH and Eh dependent, therefore the impact of these geochemical transients on retention must be quantitatively evaluated to check the performance of each barrier for realistic in-situ situations. To assess this impact, two types of engineered barriers (clay and cement) for a spent fuel repository are simulated with a coupled hydrogeochemical model. Comparisons between hydraulic heterogeneous (fractured) and simple homogeneous systems are also carried out in terms of waste dissolution.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1 Le stockage direct des combustibles irradiés, Commisariat á l'Energie Atomique, Report N° DCC/DIR 96-1484, 1996.Google Scholar
2 Lous, K. Le, Thesis, Paris XI University, 1997.Google Scholar
3 Ollar, P., Lucille, P-L, Burnol, A., Architecture du code couplé chimie-transport Chemtrap - Exercices d'application et programme de travail, Electricité de France, Report N° HT-45/97/027/B, 1997.Google Scholar
4 CHEMVAL 2: A coordinated research initiative for evaluating and enhancing chemical models in radiological risk assessment, Contract N’ F12W-CT91-0065, Nuclear Science and Technology, 1996.Google Scholar
5 Yeh, G. and Tripathi, V., Water Resour. Res. 25(1), 93108 (1989).Google Scholar
6 Lucille, P-L., Development of hydrogeochemical model for radionuclide migration, Proceedings of the 27th Congress of the Int'l Assoc. for Hydraulic Research, San Francisco, 1997.Google Scholar
7 Moulin, C. and Petitjean, A., Development of water quality models within the TELEMAC system and recent applications, Proceedings of the Second International Conference on hydroinformatics, Zürich, 1996.Google Scholar
8 Lee, J. Van der, Chess, another speciation and surface complexation computer code, Centre d'Infornatique Ggologique, Ecole des Mines de Paris, Report N° LHM/RD/96/41, 1996.Google Scholar
9 Stammose, D. et al., Applied Clay Science 7, 225238 (1992).Google Scholar
10 Krupka, K.M. and Serne, R.J., Effects on radionuclide concentrations by Cement/Ground-Water Interactions to Support Performance Assessment of Low-Level Radioactive Concentrations by Cement/Ground-Water Interactions, NUREG/CR-6377, 1996.Google Scholar
11 Maugis, P., Stietel, A., Moéglisation préliminaire du terme source stockage direct, Commissariat à l'Energie Atomique, Report N0 DMT 95/647, 1995.Google Scholar