1. General Model Information

Name: SATurated-Unsaturated flow and RadioNuclide transport

Acronym: SATURN

Main medium: terrestrial
Main subject: hydrology
Organization level: ecosystem
Type of model: partial differential equations
Main application:
Keywords: unsaturated flow, solute transport


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Huyakorn, P.S., S.D. Thomas, J.W. Mercer, and B.H. Lester


SATURN (SATurated-Unsaturated flow and RadioNuclide transport) is a two-dimensional finite element model to simulate steady-state or transient, single phase fluid flow and advective-dispersive transport in fully- or partially saturated, anisotropic, heterogeneous porous media. The flow problem is solved using the Galerkin method to approximate the Richard's equation, and a fully implicit scheme for the time domain. The resulting nonlinear algebraic equations are solved using either the Picard or Newton-Raphson iterative techniques. Soil hydraulic functions are entered either in functional or tabular form. It uses the upstream-weighted residual method to treat the transport equation. It allows the use of both triangular and quadrilateral elements. Darcy fluxes are calculated in the center of the elements causing discontinuities in fluxes across elements and local mass balance inaccuracies.

Nodal coordinates for SATURN may be generated by SATURN itself (for simple rectangular geometry) or by STRPGN, a separate mesh generator.

II. Technical Information

II.1 Executables:

Operating System(s):

II.2 Source-code:

Programming Language(s): Fortran, proprietary

II.3 Manuals:

II.4 Data:

III. Mathematical Information

III.1 Mathematics

III.2 Quantities

III.2.1 Input

III.2.2 Output

IV. References

V. Further information in the World-Wide-Web

VI. Additional remarks

The codes UNSAT2, BIM2D/3D, TRUST, FEMWATER, TOUGH, SUTRA, SATURN, TRACR3D, and FLAMINCO are described and compared in: Yeh, T.C., T.C. Rasmussen and D.D. Evans. 1988. Simulation of Liquid and Vapor Movement in Unsaturated Fractured Rock at the Apache Leap Tuff Site: Models and Strategies. NUREG/CR-5097, U.S. Nuclear Regulatory Commission, Washington, D.C. This report includes a detailed description of the code characteristics and evaluates their applicability based on governing equations and code options.
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last modified by Tobias Gabele Wed Aug 21 21:44:49 CEST 2002

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