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Arest-Ct: A New Chemical Transport code for Waste Disposal System Performance Analysis

Published online by Cambridge University Press:  15 February 2011

B. P. McGrail ,
C. I. Steefel ,
J. A. Fort ,
D. W. Engel  and
S. B. Yabusaki
B. P. McGrail
Affiliation:
Pacific Northwest Laboratoiy(a), P.O. Box 999, Richland, Washington, 99352
C. I. Steefel
Affiliation:
Pacific Northwest Laboratoiy(a), P.O. Box 999, Richland, Washington, 99352
J. A. Fort
Affiliation:
Pacific Northwest Laboratoiy(a), P.O. Box 999, Richland, Washington, 99352
D. W. Engel
Affiliation:
Pacific Northwest Laboratoiy(a), P.O. Box 999, Richland, Washington, 99352
S. B. Yabusaki
Affiliation:
Pacific Northwest Laboratoiy(a), P.O. Box 999, Richland, Washington, 99352
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Abstract

A new computer code, Analysis of RadionuclidESource-Term with Chemical Transport (AREST-CT), is described in this paper. The code is being designed to support performance assessment analyses of engineered systems for subsurface isolation of hazardous and radioactive wastes. Radionuclide releases from an engineered system are modeled by solving governing equations describing conservation of water mass, air mass, thermal energy, and chemical species mass. As such, the AREST-CT code will be capable of simulating radionuclide release and transport in a non-isothermal, unsaturated-saturated setting. Constituitive equations are implemented that describe corrosion of iron-based container materials, glass, and spent fuel waste forms. The governing equations are solved in a two-dimensional domain using an integrated finite-volume method. A third-order total variation diminishing (TVD) numerical scheme is evaluated to minimize numerical oscillations and dissipation of steep concentration gradients in advection-dominated transport problems.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 353: Symposium – Scientific Basis for Nuclear Waste Management XVIII , 1994 , 551
Copyright
Copyright © Materials Research Society 1995

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References

REFERENCES

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