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NESC9673 WAPPA.

WAPPA, Waste Package Performance Assessment

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1. NAME OR DESIGNATION OF PROGRAM:  WAPPA.
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2. COMPUTERS
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Program name Package id Status Status date
WAPPA NESC9673/01 Tested 13-AUG-1987

Machines used:

Package ID Orig. computer Test computer
NESC9673/01 DEC VAX 11/780 DEC VAX 11/780
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3. DESCRIPTION OF PROGRAM OR FUNCTION

WAPPA the Waste Package Performance Assessment program, is intended to serve as a tool for evaluating both the relative and the absolute performance of waste package design concepts, for guiding or selecting a preliminary design among conceptual designs, and for support of licensing activities. WAPPA is a barrier degradation code for a nuclear waste  package in a geologic repository. The WAPPA model includes five distinct degradation process models (radiation, thermal, mechanical, corrosion, and leaching), which are driven internally by waste decay and externally by repository stress and fluids. The modeling approach is barrier-integrated and process-sequential, allowing modification of the entire waste package by the sequential operation of five process models within each time-step. The process models are coupled at the system level via state and coupling variables. The penetration of water into the waste package and its effects on the barriers it contacts are tracked radially inwards. The WAPPA model describes and predicts the temporal and spatial extent of the loss of containment capability for each barrier and for the entire waste  package, on any time scale up to one million years after isolation.
Input includes the radial geometry and material properties of each component, degradation rates for each process modeled, and time-dependent boundary conditions (fluid flux, mechanical stress, and temperature) as the waste package/repository interface. The output quantifies the residual state of integrity of waste package components as a function of time and calculates the heat and radionuclide fluxes output to the repository. Other output at each calculation time point includes: the temperature and nuclide concentration profiles internal to the waste package, residual mass  fractions of radionuclides in the wasteform and residual waste mass  fraction, and various barrier status degradation indices andparameters. In addition, summary output includes the total mass for  each nuclide output to the repository and the barrier's status history used to pinpoint times of failure.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:  The sample problem required 16 CPU seconds.
NESC9673/01
NEA-DB executed the test case included in this package  on a VAX-11/780 computer in 285 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The fluid flux required as an input boundary condition to WAPPA can be calculated by STFLO (NESC 9852) as a function of time and stored in the geology- specific boundary conditions file. Similarly, the DOT-BPMD (NESC 9833) program can be  used at the front-end to simulate time-dependent temperatures at the waste package/repository boundary.
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9. STATUS
Package ID Status date Status
NESC9673/01 13-AUG-1987 Tested at NEADB
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10. REFERENCES:
NESC9673/01, included references:
- INTERA Environmental Consultants, Inc.:
  WAPPA: A Waste Package Performance Assessment Code.
  ONWI-452  (April 1983)
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11. MACHINE REQUIREMENTS:
NESC9673/01
1156 pages (VAX-11/780).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC9673/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  VMS.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

          G. Kilshtok
          Office of Nuclear Waste Isolation
          Battelle Project Management Division
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16. MATERIAL AVAILABLE
NESC9673/01
File name File description Records
NESC9673_01.001 Information file 92
NESC9673_01.002 WAPPA FORTRAN source 12844
NESC9673_01.003 Sample input 21
NESC9673_01.004 Sample output (FT06) 1910
NESC9673_01.005 Material codes 16
NESC9673_01.006 Repository boundary conditions 8
NESC9673_01.007 R-Gamma buildup factors and G-ray X-sct 17
NESC9673_01.008 ORIGEN2 data 139
NESC9673_01.009 Thermal properties 85
NESC9673_01.010 Mechanical properties 7
NESC9673_01.011 Fluid independent corrosion properties 20
NESC9673_01.012 Fluid dependent corrosion properties 160
NESC9673_01.013 Corrosion enhancement factors 20
NESC9673_01.014 Wasteform leach properties 1
NESC9673_01.015 Backfill leach properties 1
NESC9673_01.016 Nuclide transport properties 24
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17. CATEGORIES
  • R. Environmental and Earth Sciences

Keywords: decay, radioactive waste storage.