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
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
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.