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IAEA1370 TRIGLAV.

TRIGLAV, Research Reactor Calculations

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1. NAME OR DESIGNATION OF PROGRAM:  TRIGLAV.
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2. COMPUTERS
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Program name Package id Status Status date
TRIGLAV IAEA1370/02 Tested 11-AUG-2001

Machines used:

Package ID Orig. computer Test computer
IAEA1370/02 IBM PC PC Pentium
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3. DESCRIPTION OF PROGRAM OR FUNCTION

A computer program for reactor calculations of mixed cores in TRIGA Mark II research reactor. It can be applied for fuel element burn-up calculations, for power and flux distributions calculations and for reactivity predictions.
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4. METHODS

Program is based on four group time independent diffusion equation in two dimensional cylindrical (r, theta) geometry. Diffusion equation is solved using finite differences method with iteration of fission density.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME:  20 minutes on Intel Pentium 200MHz PC computer.
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS

TRIGLAV program needs installed WIMS-D4 program with original WIMS cross-section library extended for TRIGA reactor specific nuclides. It includes the code TRIGAC.
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9. STATUS
Package ID Status date Status
IAEA1370/02 11-AUG-2001 Tested at NEADB
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10. REFERENCES
IAEA1370/02, included references:
- A. Persic, M. Ravnik, S. Slavic and T. Zagar:
TRIGLAV, A Program Package for Research Reactor Calculations
IJS-DP-7862, Version 1  (March 28, 2000)
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11. HARDWARE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1370/02 FORTRAN-77
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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  Standard.
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15. NAME AND ESTABLISHMENT OF AUTHORS

  Andreja PERSIC, Matjaz RAVNIK, Slavko SLAVIC, Tomaz ZAGAR
  Andrej Trkov (developed the TRIGA specific library)
  "Jozef Stefan" Institute,
  Reactor physics division
  Jamova 39, PO. BOX 3000
  1001 Ljubljana, Slovenia

  E-mail: tomaz.zagar@ijs.si
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16. MATERIAL AVAILABLE
IAEA1370/02
TRIGLAV.PDF program manual in electronic form
TRIPRES.PDF Program presentation (slides)
TRIGLAV.BAT TRIGLAV MS-DOS command procedure
test1.tin Test 1 input file (test 1-fresh fuel- measured reactivity 1.00266)
test1e.tin Test 1 element input file
test1.tou Test 1 output file
test2.tin Test 2 input file (test 2-burned fuel- measured reactivity 1.00458)
test2e.tin Test 2 element input file
test2.tou Test 2 output file
test3.tin Test 3 input file (test 3-mixed core, sample input from manual)
test3e.tin Test 1 element input file
test3.tou Test 3 output file
PUTRIGL.BAT command procedure for purging scratch files
Source codes
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17. CATEGORIES
  • K. Reactor Systems Analysis

Keywords: burnup, flux distribution, fuel elements, power distribution, reactivity.