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NESC9811 SWENT.

SWENT, 3-D Fluid, Heat, Radionuclide Transport in Heterogeneous Geologic Medium

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1. NAME OR DESIGNATION OF PROGRAM:  SWENT.
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2. COMPUTERS
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Program name Package id Status Status date
SWENT NESC9811/01 Tested 04-AUG-1988

Machines used:

Package ID Orig. computer Test computer
NESC9811/01 CDC CYBER 176 CDC CYBER 830
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3. DESCRIPTION OF PROGRAM OR FUNCTION

SWENT (Simulator for Water, Energy, and Nuclide Transport) simulates the transient transport of  fluid, heat, an inert component, and any number of radionuclides through a heterogeneous geologic medium either in three dimensional  or radial geometries. The first three transport processes are coupled by the fluid properties of density and viscosity. The velocity field is derived from the solution of the coupled processes and used in the fourth process. Since radionuclides are present in trace quantities only, this process is not coupled to the first three. Aquifer porosity is treated as a function of pressure.
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4. METHOD OF SOLUTION

The resulting system of nonlinear partial differential equations is solved by finite-difference approximations, suitable linearization schemes, and an iterative technique to reduce the errors that arise in linearization.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

In the current release, the simulations are limited to maxima of 20 wells, 7 overburden vertical layers, 7 underburden vertical layers, 50 entries in the aquifer influence function tables, and 10 entries in  each of the viscosity versus temperature and concentration tables.
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6. TYPICAL RUNNING TIME:
NESC9811/01
NEA-DB ran the test cases included in this package on a CDC CYBER 830 computer. Execution time varied for the different cases from 5 seconds to 10 minutes.
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7. UNUSUAL FEATURES OF THE PROGRAM

Options are available which permit simulation of any one of the individual processes or coupled combinations of the processes. A special option is available to treat steady-state fluid flow with transient radionuclide transport. SWENT offers a wide choice in the specification of boundary conditions.
To provide control of numerical diffusion and overshoot or undershoot, the model permits the choice of backward or central difference approximations in the time-integration scheme and in the  convective terms of the transport processes. Either direct or iterative techniques may be selected for the solution of matrix equations, as appropriate, from considerations of storage and time requirements.
The three-dimensional simulation capability of the model can be adapted to a simulation of the fractured medium in one and two dimensions. The capability to link SWENT to PABLM (NESC Abstract 926), a dose-to-man code, is incorporated.
The program can be used in a wide variety of ground-water applications. When operated sequentially with PABLM it can be used to address the complete assessment of the site subsystem, and since  it models coupled processes, it is suitable for various repository assessments.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NESC9811/01 04-AUG-1988 Tested at NEADB
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10. REFERENCES:
NESC9811/01, included references:
- INTERA Environnemental Consultants, Inc. :
  SWENT: A Three-Dimensional Finite-Difference Code for the
  Simulation of Fluid, Energy, and Solute Radionuclide Transport
  ONWI-457 (April 1983)
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11. MACHINE REQUIREMENTS:  70K words.
NESC9811/01
2,722,000 (octal) words on CDC CYBER 830 (with fixed core memory allocation).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC9811/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  SCOPE and NOS.
NESC9811/01
NOS2.5.1 (CDC CYER 830).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

          M.J. Golis
          Office of Nuclear Waste Isolation
          Battelle Project Management Division
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16. MATERIAL AVAILABLE
NESC9811/01
File name File description Records
NESC9811_01.001 Information file 86
NESC9811_01.002 JCL and control information 46
NESC9811_01.003 SWENT FORTRAN source 14678
NESC9811_01.004 Nuclide data library 284
NESC9811_01.005 CONVRT FORTRAN source 20
NESC9811_01.006 Sample problem 1 132
NESC9811_01.007 Sample problem 2 198
NESC9811_01.008 Verfication test 1, Cartesian case 97
NESC9811_01.009 Verfication test 1, radial case 97
NESC9811_01.010 Verfication test 2, Cartesian case 114
NESC9811_01.011 Verfication test 2, radial case 111
NESC9811_01.012 Verfication test 3 50
NESC9811_01.013 Verfication test 4 55
NESC9811_01.014 Verfication test 5 52
NESC9811_01.015 Verfication test 6 62
NESC9811_01.016 Verfication test 8 88
NESC9811_01.017 Verfication test 9 71
NESC9811_01.018 Sample problem 1 output 2772
NESC9811_01.019 Sample problem 2 output 2680
NESC9811_01.020 Verification test 1 output 1282
NESC9811_01.021 Verification test 1 output, radial case 948
NESC9811_01.022 Verification test 2 output, Cartesian case 1385
NESC9811_01.023 Verification test 2 output, radial case 1049
NESC9811_01.024 Verification test 3 692
NESC9811_01.025 Verification test 4 665
NESC9811_01.026 Verification test 5 1406
NESC9811_01.027 Verification test 6 1379
NESC9811_01.028 Verification test 8 8280
NESC9811_01.029 Verification test 9 1133
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17. CATEGORIES
  • R. Environmental and Earth Sciences

Keywords: chemical reactions, fluid flow, heat transfer, radioactive waste storage.