Computer Programs
NEA-1231 REFREP.
last modified: 07-DEC-1989 | catalog | categories | new | search |

NEA-1231 REFREP.

REFREP, Near-Field Model for Spent Fuel Repository

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1. NAME OR DESIGNATION OF PROGRAM:  REFREP.
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2. COMPUTERS

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Program name Package id Status Status date
REFREP NEA-1231/01 Tested 07-DEC-1989

Machines used:

Package ID Orig. computer Test computer
NEA-1231/01 DEC VAX series DEC VAX 8810
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3. DESCRIPTION OF PROGRAM OR FUNCTION

A near field model for a spent  fuel repository. The program calculates mass flows of corroding species and radionuclides (actinides) in the near field of a canister in a crystalline rock repository. Inventories and release rates are calculated as a function of time for a given initial inventory. Species are assumed to diffuse through the backfill and to be carried by the groundwater flowing in rock fissures around the disposal hole. Congruent as well as non-congruent release from the fuel matrix can be considered. Release rates from canisters can be summed up using different probability distributions for canister breaching times.
The program is interactive. Input values are also included in the input files. Semsitivity analysis on the breaching times of the canisters and on the radionuclide release rates can be performed for any input parameter.
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4. METHOD OF SOLUTION:  Mathematical algorithms are presented in the references.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

1...10 seconds of CPU-time.
NEA 1231/01: NEA-DB ran the tests included in this package in interactive mode on a DEC VAX 8810 computer.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-1231/01 07-DEC-1989 Tested at NEADB
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10. REFERENCES:
NEA-1231/01, included references:
- A. Hautojarvi and T. Vieno:
  REFREP - A Near-Field Model for a Spent Fuel Repository
  YJT-88-07 (May 1988).
- A. Hautojarvi:
  Simplified Modeling of Mass Transport in a Fissured Rock - Clay
  Buffer System
  Paper Presented in the Workshop on Artificial Clay Barriers for
  High Level Radioactive Waste Repositories, Lund, Sweden, October
  5-7, 1988.
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11. MACHINE REQUIREMENTS:
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1231/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

Operating system  is standard MicroVax II system with VMS 4.7. SLATEC-library was linked to calculate the error function erf(x). Erf(x) could be easily programmed as a subroutine (or function) using well known approximations.
NEA-1231/01
VMS version V5.-01 (VAX 8810).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The DO- loops have to be rewritten in a standard form for an operating system or compiler that does not know the structure DO ... ENDDO. Otherwise the program should be ready to be compiled in another system than MicroVax II.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          A. Hautojarvi and T. Vieno
          Technical Research Centre of Finland (VTT)
          Nuclear Engineering Laboratory
          P.O.B 169
          SF-00181 Helsinki, Finland
The program was developed on a commission to the Industrial Power
Company Ltd (TVO).
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16. MATERIAL AVAILABLE
NEA-1231/01
File name File description Records
NEA1231_01.001 Information file 197
NEA1231_01.002 REFREP main program 61
NEA1231_01.003 Subprogram CONGRUENT.FOR 182
NEA1231_01.004 Subprogram CORRFLUX.FOR 372
NEA1231_01.005 Subprogram DATAOUT.FOR 124
NEA1231_01.006 Subprogram ELEMENT.FOR 246
NEA1231_01.007 Subprogram ERF.FOR 1581
NEA1231_01.008 Subprogram INVENT.FOR 149
NEA1231_01.009 Subprogram MASSFLUX.FOR 185
NEA1231_01.010 Subprogram PROBDIS.FOR 159
NEA1231_01.011 Subprogram PROBREL.FOR 74
NEA1231_01.012 Subprogram SENSIT.FOR 604
NEA1231_01.013 Subprogram STEP.FOR 142
NEA1231_01.014 Subprogram UPDATE.FOR 108
NEA1231_01.015 Data files CAPSM.DAT 5
NEA1231_01.016 Data files CORRCONC.DAT 6
NEA1231_01.017 Data files CORRDIFF.DAT 7
NEA1231_01.018 Data files DIFFCOEF.DAT 5
NEA1231_01.019 Data files FILENAMES.DAT 6
NEA1231_01.020 Data files MASSFLUX.DAT 7
NEA1231_01.021 Data files SOLUB.DAT 8
NEA1231_01.022 Data files REFREP.TXT 23
NEA1231_01.023 Data files INVENT.INP 49
NEA1231_01.024 Data files RELEASE.DAT 1000
NEA1231_01.025 Data files PROBDIS.DAT 1001
NEA1231_01.026 Sample output files CURRFLUX.OUT 59
NEA1231_01.027 Sample output files MASSFLUX.OUT 24
NEA1231_01.028 Sample output files INVENT.OUT 45
NEA1231_01.029 Sample output files CONGRUENT.OUT 43
NEA1231_01.030 Sample output files SENSIT.OUT 57
NEA1231_01.031 Sample output files ELEMENT.OUT 43
NEA1231_01.032 Sample output files PROBREL.OUT 118
NEA1231_01.033 Sample output files INPDATA.OUT 62
NEA1231_01.034 Additional information 78
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • R. Environmental and Earth Sciences

Keywords: actinides, nuclear fuels, radioactive release, radioactive waste storage, sensitivity analysis.