Computer Programs
IAEA1338 TEMPUL.
last modified: 10-OCT-1997 | catalog | categories | new | search |

IAEA1338 TEMPUL.

TEMPUL, Temperature Distribution in Fuel Element after Pulse

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1. NAME OR DESIGNATION OF PROGRAM:  TEMPUL.
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2. COMPUTERS
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Program name Package id Status Status date
TEMPUL IAEA1338/01 Tested 10-OCT-1997

Machines used:

Package ID Orig. computer Test computer
IAEA1338/01 Many Computers Many Computers
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3. DESCRIPTION OF PROGRAM OR FUNCTION

A computer program for temperature distribution calculations in fuel element after the pulse.
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4. METHOD OF SOLUTION

The program solves the diffusion equation for heat transfer in one-dimensional cylindrical geometry using simple finite-difference method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The program is provided with THE necessary data-base consisting of material properties for : 1-zirconium, 2-stainless steel, 3-fuel with 12 w/o  uranium and 20% enrichment, 4-fuel with 8.5 w/o uranium and 20% enrichment, 5-FLIP fuel with 8.5 w/o uranium and 70% enrichment, 6-LEU fuel with 20 w/o uranium and 20% enrichment and 7-water. The gap can either be filled with air or with Helium. The gap also can be omitted.
The number of output-times for the radial temperature distribution is limited to 11.
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6. TYPICAL RUNNING TIME:
IAEA1338/01
Two hours on Intel 486/100 computer; 30 minutes on a
VAX 4000; 15 minutes CPU-time on a Pentium 166MHz; 10 minutes on DEC ALPHA computer.
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7. UNUSUAL FEATURES OF THE PROGRAM

TEMPUL generates output for the DIAG program CITEDIAG. With this output a graphical representation of the output data is possible.
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8. RELATED AND AUXILIARY PROGRAMS:  WIMS-D/4; DIAG.
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9. STATUS
Package ID Status date Status
IAEA1338/01 10-OCT-1997 Tested at NEADB
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10. REFERENCES

- Varnostno porocilo za reaktor TRIGA Mark II v Podgorici
  IJS-DP-5823,
  January 1991
- Safety Analysis Report for the 3000-kW Forced-Flow TRIGA Mark II
  Reactor for the Bangladesh Atomic Energy Commission
  Dacca, Bangladesh
  General Atomic, E-117-990, July 1981
- M.Ravnik, I.Mele, B.Zefran, PULSTRI-1 A Computer Programme
  for TRIGA Reactor Pulse Calculations,
  J.Stefan Institute Report,IJS-DP-5756, Jan. 1990
- I.Mele, M.Ravnik, TRIGAP Computer Programme, J.Stefan
  Institute Report, IJS-DP-4238, Dec. 1985
- I. Mele, M. Ravnik
  Projekt rekonstrukcije reaktorja TRIGA za pulzno obratovanje
Preracun nuklearnih lastnosti, Revizija 1, IJS-DP-5760, Marec 1990  - L. S. Tong, J. Weisman
  Thermal Analysis of Pressurized Water Reactors,
  American Nuclear Society and U.S. Atomic Energy Commission, 1971
- E.L. Wachpress
  Iterative Solution of Elyptic Systems and Applications
  to the Neutron Diffusion Equations of Reactor Physics
  Prentice-Hall, Inc., Englewood Cliffs, N.J., USA, 1966
- DIAG, 2-D Plotting Program for PDP-11/34, IAEA0891, NEA Data Bank
- WIMS-D/4, NEA Data Bank
IAEA1338/01, included references:
- I. Mele, S. Slavic and M. Ravnik:
  TEMPUL - A Computer Program for Temperature Distribution
  Calculations in Fuel Element after the Pulse
  Program Manual
  IJS-DP-6523 (October 1992)
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11. MACHINE REQUIREMENTS:
IAEA1338/01
Output files can, depending on input options, require very much space.  Minimum disk space for all files IS 1.3 MB.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1338/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
IAEA1338/01
MS-DOS, MS-WINDOWS, Open VMS, Unix
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.
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15. NAME AND ESTABLISHMENT OF AUTHORS

    Slavko Slavic, Matjaz Ravnik
    "Jozef Stefan" Institute,
    Reactor physics division
    Jamova 39, PO. BOX 3000
    1001 Ljubljana, Slovenia
    E-mail: Slavko.Slavic@ijs.si
    E-mail: Matjaz.Ravnik@ijs.si
    and:
    Irena Mele
    Agencija za radioaktivne odpadke
    Parmova ulica 53
    1000 Ljubljana, Slovenia
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16. MATERIAL AVAILABLE
IAEA1338/01
File name File description Records
IAEA1338_01.001 information file 125
IAEA1338_01.002 sample output of test case 1 0
IAEA1338_01.003 sample input for test case 1 0
IAEA1338_01.004 sample output of test case 1 0
IAEA1338_01.005 sample output of test case 1 0
IAEA1338_01.006 sample output of test case 1 0
IAEA1338_01.007 sample output of test case 2 0
IAEA1338_01.008 sample input for test case 2 0
IAEA1338_01.009 sample output of test case 2 0
IAEA1338_01.010 sample output of test case 2 0
IAEA1338_01.011 sample output of test case 2 0
IAEA1338_01.012 list of files 0
IAEA1338_01.013 PC (MS-)DOS executable 0
IAEA1338_01.014 FORTRAN source code 0
IAEA1338_01.015 DOS file-names 15
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • H. Heat Transfer and Fluid Flow

Keywords: fuel elements, temperature distribution.