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IAEA1274 AIREKMOD-RR.

AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors

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1. NAME OR DESIGNATION OF PROGRAM:  AIREKMOD-RR.
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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
AIREKMOD-RR IAEA1274/01 Arrived 28-MAR-2001

Machines used:

Package ID Orig. computer Test computer
IAEA1274/01 DEC VAX series
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3. DESCRIPTION OF PROGRAM OR FUNCTION

AIREMOD-RR is a point kinetics  code which can simulate fast transients in nuclear research reactor  cores. It can also be used for theoretical reactor dynamics studies. It is used for research reactor kinetic analysis and provides a point neutron kinetic capability. The thermal hydraulic behavior is  governed by a one-dimensional heat balance equation. The calculations are restricted to a single equivalent unit cell which consists of fuel, clad and coolant.
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4. METHOD OF SOLUTION

For transient reactor kinetic calculations a modified Runge Kutta numerical method is used. The external reactivity insertion, specified as a function of time, is converted  in dollar ($) unit. The neutron density, energy release and feedback variables are given at each time step. The two types of reactivity feedback considered are: Doppler effect and moderator effect. A new  expression for the reactivity dependence on the feedback variables has been introduced in the present version of the code. The feedback reactivities are fitted in power series expression.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The number of delayed neutron groups and the total number of equations are limited only by computer storage capabilities.
- Coolant is always in liquid phase.
- Void reactivity feedback is not considered.
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6. TYPICAL RUNNING TIME

Less than 20 sec are required for a sample problem related to fast reactivity insertion.
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7. UNUSUAL FEATURES OF THE PROGRAM:  Can be run on Personal Computers (P.C.).
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8. RELATED AND AUXILIARY PROGRAMS:  AIREKMOD-RR is a modified version of the AIREK-MOD Code.
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9. STATUS
Package ID Status date Status
IAEA1274/01 28-MAR-2001 Masterfiled Arrived
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10. REFERENCES

- B. Baggoura and H. Mazrou:
  AIREKMOD-RR - A Point Kinetic Computer Code for Reactivity
  Transient Analysis in Nuclear Research Reactors
  C.D.S.E./D.P.S.S.E. (1992) report to be published.
- C. Tamagnini:
  AIREK-MOD - A Modified Version of the Kinetic Code AIREK-II
  EUR 1914.E.
- E.R. Cohen:
  Some Topics in Reactor Kinetics
  Proc. Second Int. Conf. PUA, 11, 302-309 (1958).
- B 17681 ANJE0120 Job0120 ANLCV1. Output du Code PARET en date du
  15/05/1990.
- IAEA Safety and Licensing Guidebook of Research Core Conversion
  from the Use of High Enriched Uranium (HEU) to the Use of Low
  Enriched Uranium (LEU), Volume 3: Appendixes (G-H), Vienna,
  Austria (1990).
- Research Reactor Core Conversion from the Use of High Enriched
  Uranium (HEU) to the Use of Low Enriched (LEU) Fuels Guidebook
  IAEA-TECDOC-233 (1980).
IAEA1274/01, included references:
- A Point Kinetic Computer Code for Reactivity Transient Analysis in
  Nuclear Research Reactors
  AIREKMOD-RR User's Guide.
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11. MACHINE REQUIREMENTS

The sample problem requires less than 200 Kbytes. For special plotting files more spaces is needed (<= 350 Kbytes).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1274/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  VAX/VMS.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  No
additional informations are required.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          B. Baggoura
     Centre de Radioprotection et de Surete (CRS)
     2 Boulevard Frantz Fanon
     B.P. 1017 Alger Gare, Alger 16000, Algeria

          H. Mazrou
     Centre de Developpement des Systemes Energetiques (CDSE)
     B.P. 180 Ain-Oussera, 17200, Algeria
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16. MATERIAL AVAILABLE
IAEA1274/01
source program   mag tapeAIREKMOD.FOR AIREKMOD Source File          SRCTP
test-case output mag tapeAIREKMOD.OUT AIREKMOD Output File          OUTTP
test-case data   mag tapeHEU.DAT AIREKMOD Test-Case Data            DATTP
user's guide             AIREKMOD-RR User's Guide                   WRKPT
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: loss-of-coolant accident, reactor kinetics.