Hostname: page-component-586b7cd67f-rdxmf Total loading time: 0 Render date: 2024-11-29T09:49:51.487Z Has data issue: false hasContentIssue false

Near-Field Thermal Analysis of the Nuclear Waste Disposal Vault

Published online by Cambridge University Press:  28 February 2011

H. S. Radhakrishna
Affiliation:
Ontario Hydro, Research Div., 800 Kipling Ave., Toronto, Canada
K-C. Lau
Affiliation:
Strata Engineering Corp., Toronto, Canada
A. M. Crawford
Affiliation:
University of Toronto, Dept. of Civil Eng., Toronto, Canada
Get access

Abstract

This paper describes an experimental and theoretical analysis of the near-field thermal performance of a backfilled disposal vault in which the waste containers are emplaced in boreholes and surrounded by a bentonite-sand buffer. Effects of heat and moisture diffusion on the thermal performance of clay-based buffer and backfills were studied by means of laboratory scale experiments. The bentonite-sand buffer exhibited cracking due to desiccation. The impact of such cracking on the perforamnce of buffer as an engineered barrier is being investigated.

An integrated finite difference computer code ‘TRUCHAM’ was written to analyze the transient heat and moisture flow regime in a disposal vault and was validated by a scale model heater experiment. It is hoped that with proper characterization of the material properties ‘TRUCHAM’ can be employed as a useful tool in assessing the thermal response of the prototype disposal vault. Further work is needed to integrate the effects of heat and moisture on the shrinkage and expansion of clay-based buffer and backfills.

Type
Research Article
Copyright
Copyright © Materials Research Society 1985

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

1. Boulton, J. (Editor), “Management of Radioactive Fuel Wastes”: The Canadian Disposal Program, Atomic Energy of Canada Limited Report, AECL-6314 (1978).Google Scholar
2. Acres Consulting Services Ltd. and Associates, “A Disposal Centre for Irradiated Nuclear Fuel: Conceptual Design Study”, Atomic Energy of Canada Limited Report, AECL-6415 (1980).Google Scholar
3. Lopez, R.S., Cheung, S.C.H. and Dixon, D.A., “Geotechnical Aspects of the Sealing of Underground Nuclear Fuel Waste Vaults”, Technical Note, Canadian Geotechnical Journal, No. 3, Vol.21 (1984).Google Scholar
4. Radhakrishna, H.S., “Thermal Properites of Clay-based Buffer Materials for Nuclear Fuel Waste Disposal Vault”, Atomic Energy of Canada Limited, AECL-7805 (1984).Google Scholar
5. Abdel-Hadi, O.N., “Flow of Heat and Water Around Underground Power Cables”, Ph.D. Thesis presented to the University of California, Berkeley, California (1978).Google Scholar
6. Phillip, J.R. and DeVries, D.A., “Moisture Movement in Porous Materials Under Temperature Gradients”, Trans American, Geophysical Union 38, (The American Geophysical Union of the National Academy of Sciences, Washington, DC, 1957) pp. 222232.Google Scholar
7. Cassel, D.S., Nielson, D.R. and Biggar, J.W., “Soil Water Movement in Response to Imposed Temperature Gradients”, Soil Science Society of America, Vol.33 (1969).Google Scholar
8. Radhakrishna, H.S., Lau, K.C. and Crawford, A.M., “Coupled Heat and Moisture Flow through Soils”, Journal of Geotechnical Eng., American Society of Civil Engineers, Vol.110, No. 12 (1984).Google Scholar