Hostname: page-component-78c5997874-j824f Total loading time: 0 Render date: 2024-11-08T00:39:09.461Z Has data issue: false hasContentIssue false

The Leaching Behavior of Bituminized Radioactive Waste in the Geologic Disposal Conditions of the Boom Clay Formation

Published online by Cambridge University Press:  10 February 2011

A. Sneyers
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
P. Van Iseghem
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
Get access

Abstract

As part of the evaluation of the safety of geologic disposal, the leaching behaviour of two types of bituminized radioactive waste (Eurobitum and CEA bitumen) has been studied as a function of temperature, pressure, leachant composition and bitumen matrix type. Inactive and active bitumen samples were brought into contact with two test media, simulating the geologic disposal environment of the Boom clay formation. At contact with these media, the samples swelled and soluble salts and radionucides were leached. It was found that the leach rate is influenced by temperature, the leachant composition, and the physical characteristics of the bitumen matrix. The release of nitrate is interpreted as a diffusion controlled process, which can however be disturbed by crack formation. The leaching of 60Co, 90Sr, and total β is diffusion controlled. Low leach rates were measured for Pu and Am: the release of Pu and Am is limited by their solubility in the leachant. Pu and Am are preferentially sorbed to the Boom clay, the test container or the bitumen. The leached mobile Pu and Am concentrations are of the order of 10−10 to 1013 M at 23°C. The results of this study suggest that the integrity of bituminized waste packages is seriously affected due to the leaching of soluble salts: a full-size 220 litre Eurobitum drum is predicted to be depleted in NaNO3 in less than 20,000 years.

Type
Research Article
Copyright
Copyright © Materials Research Society 1998

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 Snellman, M., Valkiainen, M., Airola, C., Brodersen, K., Forsström, H., Wingefors, S., Long term properties of bituminized waste products, Nordic liaison committee for atomic energy (nka), 1985, 88p.Google Scholar
2 Bituminization processes to condition radioactive wastes, International Atomic Energy Agency, 1993, Technical reports series, STI/DOC/10/352.Google Scholar
3 Koncept en globale kosten van de berging. Berging van het afval met lange halveringstijd en/of zeer hoge aktiviteit (kategoriën B en C) in de Boomse klei onder de site van Mol-Dessel: beschriiving van de bergingsinstallaties en raining van de globale kosten, Information letter NIRAS/ONDRAF, Brussel, 1989, 11 p.Google Scholar
4 Marivoet, J., Updating 1990. Updating of the performance assessments of the geologic disposal of high-level and medium-level wastes in the Boom clay formation, SCKSCEN and NIRAS/ONDRAF, 1991, report BLG-634.Google Scholar
5 Sneyers, A., Iseghem, P. Van. Compatibility of bituminized reprocessing waste! with geological disposal in clay. Final report to the Commission of the European Communities. To be published as EUR-report, 101 pp. In PressGoogle Scholar
6 Berghman, K., Iseghem, P. Van, Timmermans, W., The Physico-chemical stability of bituminized Eurochemic medium-level reprocessing waste, 1990, Second international seminar on radioactive waste products, Kflülich, 20 May-01 June 1990, BfS Schriften 1/90, edited by Warnecke, E., Odoj, R. and Simon, R., p. 479498.Google Scholar
7 Handbook of reference medium active waste (RMA), R&D programme on management and disposal of radioactive waste, First edition, 1989, CEC report, EUR 12482, 125 p.Google Scholar
8 Sneyers, A., Procédé et dispositif pour le prélvèement d'un échantillon hors d'une matière thermoplastique, 1995, EP 0704 690 A1. Européen. European Patent Office, 10 p.Google Scholar
9 Brunel, G., Louvat, D., Sneyers, A., Nomind, J.C., Brodersen, K., Gens, R., Properties of bituminious radioactive materials: characterization of bituminized waste and natural analogues, 1997, EUR 17543, p. 195208 Google Scholar
10 Nuclear Waste Materials Handbook. Test methods. MCC-IP Static leach test method. Pacific Northwest Laboratory, Richland, Washington, PNL-3990, p. 1–35Google Scholar
11 Mendel, J.E., A review of leaching test methods and the leachability of various solid media containing radioactive waste, 1983, report BNWL-1765, 44 pp.Google Scholar
12 Nestor, C.W., 1980. Diffusion from solid cylinders. Report ORNL/CSD/TM-84.Google Scholar
13 American National Standard Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure. American Nuclear Society, ANSI/ANS-16.1-1986, 35 pp.Google Scholar
14 Dierckx, A., Cannidre, P. De, Fonteyne, A., Gompel, M. Van, M., Transport of radionuclides due to the complexation with organic matter in Boom Clay. Progress report to NIRAS/ONDRAF for the first semester of 1995, 1995, Report R-3080 volume 2 (of 3).Google Scholar
15 Marivoet, J., Volckaert, G., Wemaere, I., Wibin, J., Evaluation of elements responsible for the effective engaged dose rates associated with the final storage of radioactive wastes: Everest project. Volume 2a: Clay formation, site in Belgium, 1997, EUR 17449/2a, 328 p.Google Scholar