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Analysis of Mass Transport in an Engineered Barriers System for the Disposal of Used Nuclear Fuel

Published online by Cambridge University Press:  21 February 2011

Nava C. Garisto  and
Dennis M. Leneveu
Nava C. Garisto
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment Pinava, Manitoba, CanadaROE ILO
Dennis M. Leneveu
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment Pinava, Manitoba, CanadaROE ILO
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Abstract

The Vault Model has been developed to assess the performance of engineered barriers in a conceptual geological disposal vault for used nuclear fuel. It represents container failure, release of radionuclides from used fuel and mass transport of released radionuclides through the clay-based sealing materials surrounding the waste containers. This paper focusses on mass-transport processes represented by the Vault Model, including diffusion, convection and retardation.

In particular, we present results of several scoping calculations carried out with the Vault Model. We consider cases where the clay-based barriers are represented by either a one- or a two-layer system adjacent to an intact rock and a case where the two clay-based barriers are adjacent to a highly fractured rock. These calculations provide insight into the model and produce test cases for comparison with both relatively simple analytical estimates and similar computer codes, as they become available. The analytical estimates generally support the Vault Model results and thus enhance our confidence in the accuracy of the Vault Model calculations.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 775
Copyright
Copyright © Materials Research Society 1990

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References

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