Hostname: page-component-848d4c4894-8bljj Total loading time: 0 Render date: 2024-06-22T12:57:01.454Z Has data issue: false hasContentIssue false

Static Leaching of Radioactive Glass Under Conditions Simulating a Granitic Repository for High-Level Waste: Phase 1.

Published online by Cambridge University Press:  25 February 2011

Hans-Peter Hermansson
Affiliation:
Studsvik Energiteknik AB, S-611 82 Nyk6ping, Sweden.
Hilbert Christensen
Affiliation:
Studsvik Energiteknik AB, S-611 82 Nyk6ping, Sweden.
David E Clark
Affiliation:
Department of Materials Science and Engineering, University of Florida, Gainesville, FL 32611, USA.
Inga-Kari Björner
Affiliation:
Studsvik Energiteknik AB, S-611 82 Nyk6ping, Sweden.
Hayaichi Yokoyama
Affiliation:
Central Research Institute of Electric Power Industry 11-1, Iwato Kita2-Chome, Komae-Shi, Tokyo, 201 Japan.
Lars Werme
Affiliation:
Swedish Nuclear Fuel Supply Co. (SKBF/KBS), P.O. Box 5864, S-102 48 Stockholm, Sweden.
Get access

Abstract

A joint research project with participation from Japan, Switzerland and Sweden is underway at Studsvik (The JSS-project). The project concerns investigations on the leaching of fully radioactive glass (containing 12 wt% fission product oxides and actinide oxides) manufactured by CEA/Marcoule.

So far the glass has been leached in doubly distilled water and in silicate water at 90°C. Some leaching experiments involved the presence of crushed Stripa granite in the same containers as the glass.

Due to strong radiation and the presence of plutonium the leaching was carried out in a specially designed lead cave using gilded stainless steel containers.

Weight losses, pH and elemental mass losses were determined together with infrared reflection spectral changes. These data are compared to those obtained from a simulated nonradioactive glass of nearly the same composition and to similar alkali borosilicate glasses previously investigated at Studsvik.

Type
Research Article
Copyright
Copyright © Materials Research Society 1984

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. Materials Characterization Center, 1981. Nuclear Waste Materials Handbook, Vol. 1. Test Methods. DOE/TIC-11400, Pacific Northwest Laboratory, Richland, Washington.Google Scholar
2. Van de Voorde, M.H. and Restat, Selection Guide to Organic Materials for Nuclear Engineering, CERN 72-7, May 17, 1972. pp 48. CERN European Organization for Nuclear Research.Google Scholar
3. Hermansson, H-P, Christensen, H., Clark, D.E. and Werme, L., “Effects of Solution Chemistry and Atmosphere on Leaching of Alkali Borosilicate Glass,” in Scientific Basis for Nuclear Waste Management VI, Ed. Brookins, D.G., Elsevier Science Publishing Co., New York, 1983.Google Scholar
4. Pederson, L.R., Buckwalter, C.O., McVay, G.L. and Riddle, B.L., “Glass Surface Area to Solution Volume Ratio and its Implications to Accelerated Leach Testing,” in Scientific Basis for Nuclear Waste Management VI, Ed. Brookins, D.G., Elsevier Science Publishing Co., New York, 1983, pp. 4754.Google Scholar
5. Strachan, D.M., “Results from a One-Year Leach Test: Long-Term Use of MCC-I,” in Scientific Basis for Nuclear Waste Management V, Ed. Lutze, W., Elsevier Science Publishing Co., New York, 1982, pp. 181191.Google Scholar
6. Clark, D.E., Pantano, C.G. Jr and Hench, L.L., Glass Corrosion, Books for Industry, 777 Third Ave., New York, N.Y., 1979.Google Scholar
7. Clark, D.E., Ethridge, E.C., Dilmore, M.F. and Hench, L.L., “Quantitative Analysis of Corroded Glass Using IRRS Frequency Shifts,” Glass Technology, 18 4, 121124 (1977).Google Scholar
8. McVay, G.L. and Pederson, L.R., “Effect of Gamma Radiation on Glass Leaching”, J.Am.Ceram.Soc., 64 3 , 154158 (1981).Google Scholar