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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 Tested 03-DEC-2014

Machines used:

Package ID Orig. computer Test computer
IAEA1274/01 DEC VAX series PC Windows
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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. METHODS

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 OR 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 03-DEC-2014 Tested at NEADB
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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. HARDWARE REQUIREMENTS

The sample problem requires less than 200 Kbytes. For special plotting files more spaces is needed (<= 350 Kbytes).

IAEA1274/01

Tested at the NEA Data Bank on a PC with 2GHz INTEL Pentium 4 with WINDOWS 7 Professional; Lahey compiler.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1274/01 FORTRAN-77
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13. SOFTWARE REQUIREMENTS

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.