A Vault Model for the Assessment of Used Fuel Disposal in Canada

Author:

Garisto N. C.,Leneveu D. M.

Abstract

AbstractThe environmental assessment of the geological disposal of used nuclear fuel involves the assimilation of experimental results to produce an estimate of the potential impact of a disposal vault on man and the environment. In this paper we briefly outline the assessment methodology and expand upon one aspect of the data assimilation process, namely, the incorporation of research results on the performance of engineered barriers into assessment models.The model to be discussed represents (i) failure modes for titaniumbased containers, including short-term failures due to undetected manufacturing defects and long-term failures due to uniform and local corrosion; (ii) release of radionuclides from used fuel, including relatively fast release of soluble fission products from gap and grain boundaries and slow, congruent release controlled by the dissolution of the fuel matrix itself; and (iii) mass transport of released radionuclides through the clay-based sealing materials surrounding the waste container, including diffusion, convection and radionuclide storage (sorption or retardation) effects.

Publisher

Springer Science and Business Media LLC

Subject

General Engineering

Reference37 articles.

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3. 12. Sorenson N.R. and Diegle R.B. , “Corrosion Research of Alloys for Use in Nuclear Waste Disposal Containers,” in The Corrosion Performance of Nuclear Fuel Waste Containers, pp. 31–40, Atomic Energy of Canada Limited Technical Record, TR-340 (1985).

4. Response function of the convection-dispersion equations describing radionuclide migration in a finite medium

5. 18. Sato H. , Kamikubo F. and Shimogori K. , “Effect of Gasket Materials on Crevice Corrosion of Titanium,” in Titanium '84, Proc. 5th Int. Conf. on Titanium, Munich, FRG, September 10–14, 1984, edited by Lutjering G. , Zwicker U. and Bunk W. (1985).

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