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Influence of the Near-Field Conditions on the Mobile Concentrations of Np and Tc Leached from Vitrified HLW

Published online by Cambridge University Press:  17 March 2011

Véra Pirlet ,
Karel Lemmens  and
Pierre Van Iseghem
Véra Pirlet
Affiliation:
Waste and disposal Department, SCK•CEN (Belgian Nuclear Research Center) Boeretang 200, B-2400 Mol, Belgium
Karel Lemmens
Affiliation:
Waste and disposal Department, SCK•CEN (Belgian Nuclear Research Center) Boeretang 200, B-2400 Mol, Belgium
Pierre Van Iseghem
Affiliation:
Waste and disposal Department, SCK•CEN (Belgian Nuclear Research Center) Boeretang 200, B-2400 Mol, Belgium
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Abstract

The solubility values usually used in Belgium for Performance Assessment of the disposal of HLW in deep geological formations are based on migration experiments in the far-field and, thus, can be considered as "far-field solubilities". The particular chemistry in the near-field of the repository will also influence the solubility of the released radionuclides. Therefore, the determination of maximum concentrations of the radionuclides in the near-field is also useful. This was approached by leach tests with doped glass in near-field conditions. The experiment consisted of static leach tests with the french R7T7 reference glass doped with 237Np (0.34 wt%) and 99Tc (0.12 wt%), two key radionuclides in the performance assessment of the disposal system. The glass was put in contact with FoCa7-clay together with pyrite, metallic iron and Boom clay water to simulate the near-field conditions under reducing conditions. The interpretation of the results is based on the measurement of the steady-state Np and Tc concentrations in the leachates after ultrafiltration through 100,000 MWCO membranes and on the activity measured on the clay after different test durations. Most of the Np and Tc activity (99.5%) was found associated to the clay and increasing as a function of time while the Np and Tc concentration in the leachates were stable and extremely low with a mean value of 1.5×10−10M for Np and 5.6×10−10M for Tc. This is due at least partially to sorption on the clay, but there are indications for precipitation as well.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC7.5
Copyright
Copyright © Materials Research Society 2004

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References

[1] Lajudie, A., Raynal, J., Petit, J-C, Toulhoat, P., Mat.Res.Soc.Symp.Proc., Vol 353, 221–231 (1995)Google Scholar
[2] Lemmens, K., Aertsens, M., Lolivier, P., Malengreau, N., Pirlet, V., Cannière, P. De, "Characterization and Compatibility with the Disposal Medium of COGEMA and Eurochemic Reprocessing Waste Forms" Tasks VM-6 and GV8 of NIRAS/ONDRAF contracts CCHO-90/123-1 and CCHO-90/123-2 (vitrified waste), Final report (1996-2000)Google Scholar
[3] Lemire, R.J., Fuger, J., Nitsche, H., Potter, P., Rand, M.H., Rydberg, J., Spahiu, K., Sullivan, J.C., Ullman, W.J., Vitorge, P., Wanner, H., Chemical Thermodynamics of Neptunium and Plutonium, Draft of 10th January 2000, version for peer review, Edited by OECD Nuclear Agency, Data Bank, Issy-Les-Moulineaux, France (2000)Google Scholar
[4] Cui, D., Eriksen, T.E., Environ. Sci. Technol., Vol 30, 2263 (1996)Google Scholar
[5] Marivoet, J., Volckaert, G., Labat, S., Cannière, P. De, Dierckx, A., Kursten, B., Lemmens, K., Lolivier, P., Mallants, D., Sneyers, A., Valcke, E., Wang, L., Wemaere, I., “Values for the near-field used in the performance assessment of the geological disposal of radioactive waste in the Boom Clay formation at the Mol site” (Volume 1 and 2), Report to NIRAS/ONDRAF, Contract CCHO-98/332-KNT 90.98.1042 task 6.1, R-3344 (July 1999).Google Scholar
[6] Berner, U., “Project Opalinus clay: [RN] limits in the near-field of a repository for spent fuel and vitrified HLW”, Report from PSI (bericht Nr 02-22, ISSN 1019-0643) (dec. 2002)Google Scholar