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IAEA1337 TRISTAN-IJS.

TRISTAN-IJS, Steady-State Axial Temperature and Flow Velocity in Triga Channel

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1. NAME OR DESIGNATION OF PROGRAM:  TRISTAN-IJS.
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2. COMPUTERS
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Program name Package id Status Status date
TRISTAN-IJS IAEA1337/01 Tested 06-APR-2000

Machines used:

Package ID Orig. computer Test computer
IAEA1337/01 Many Computers PC Pentium II 400
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3. DESCRIPTION OF PROGRAM OR FUNCTION

A computer program for calculating steady-state axial temperature distribution and flow velocity through a vertical coolant channel in low power TRIGA reactor core, cooled by natural circulation.
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4. METHOD OF SOLUTION

Stable operating point is calculated by iterations according to Bernoulli equation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:  Few seconds on Intel PC computer.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:  None.
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9. STATUS
Package ID Status date Status
IAEA1337/01 06-APR-2000 Tested at NEADB
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10. REFERENCES

- Varnostono porocilo za reaktor TRIGA Mark II v Podgorici,
  Revizija 3, IJS-DP-5832, Junij 1992
- I. Mele:
  Izracun porazdelitve moci in temperature v reaktorju TRIGA
  med tranzientom, Magisrsko delo, Univerza v Mariboru, Maj 1991
- Safety Analysis Report for the 3000 kW forced-Flow TRIGA Mark II
  Reactor for the Bangladesh Atomic Energy Commission, GA E-117-990
  July 1981
- Physics Handbook, American Institute of Physics Handbook,
  McGraw-Hill Book Company, 1982
- M. Opresnik, M. Opara:
  Termodinamicne tabele in diagrami, Fakulteta za strojnistvo,
  Ljubljana 1974
- L.S. Tong, J. Weisman:
  Thermal Analysis for Pressurized Water Reactors, American Nuclear
  Society, 1970
- M.M. El-Wakil:
  Nuclear Heat Transport, An Intext Publisher, London, 1971
IAEA1337/01, included references:
- I. Mele and B. Zefran:
  TRISTAN, A Computer Program for Calculating Natural Convection
  Flow Parameters in TRIGA Core
  Program Manual
  IJS-DP-6548 (December 1992)
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11. MACHINE REQUIREMENTS:  Intel PC with 540 K main memory.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1337/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  Standard.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.
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15. NAME AND ESTABLISHMENT OF AUTHORS

   Bojan Zefran
   "Jozef Stefan" Institute
   Reactor Physics Division
   Jamova 39, PO Box 3000
   1001 Ljubljana
   Slovenia

   Irena Mele
   Agencija za radioaktivne odpadke
   Parmova ulica 53
   1000 Ljubljana
   Slovenia
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16. MATERIAL AVAILABLE
IAEA1337/01
source program   mag tapeTRISTAN.FOR Source code                    SRCTP
source program   mag tapeTRISTANK.FOR Source code                   SRCTP
source program   mag tapeTRISTANP.FOR Source code                   SRCTP
source program   mag tapeCTSCOMP1.FOR Source code                   SRCTP
source program   mag tapeCTSINP.FOR Source code                     SRCTP
source program   mag tapeCTSMSG.FOR Source code                     SRCTP
source program   mag tapeCTSSYS.FOR Source code                     SRCTP
test-case data   mag tapeTRISTAN.MAK Sample make file               DATTP
load module      mag tapeTRISTAN.EXE TRISTAN executable (any PC)    LODTP
test-case data   mag tapeTRISTAN.TIN Test case input                DATTP
test-case output mag tapeTRISTAN.TOU Test case output               OUTTP
test-case data   mag tapeTRISTAN.VMS Sample of VAX/VMS command      DATTP
test-case data   mag tapeTRISTAN.INP Input file                     DATTP
miscellaneous    mag tapeTRISTAN.TXT List of files                  MISTP
report                   IJS-DP-6548 (December 1992)                REPPT
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • H. Heat Transfer and Fluid Flow

Keywords: flow rate, fluid flow, reactor cooling systems, steady flow, steady-state conditions, temperature distribution.