IAEA1274: AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors

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IAEA1274 AIREKMOD-RR. (Abstract last modified 28-MAR-2001)

AIREKMOD-RR, Reactivity Transients in Nuclear Research Reactors

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION OF PROGRAM - AIREKMOD-RR.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name Package-ID Status AIREKMOD-RR IAEA1274/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer IAEA1274/01 DEC VAX series

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.

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.

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.

6. TYPICAL RUNNING TIME - Less than 20 sec are required for a sample problem related to fast reactivity insertion.

7. UNUSUAL FEATURES OF THE PROGRAM - Can be run on Personal Computers (P.C.).

8. RELATED AND AUXILIARY PROGRAMS - AIREKMOD-RR is a modified version of the AIREK-MOD Code.

9. STATUS
IAEA1274/01: 28-MAR-2001 Masterfiled Arrived

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:
- A Point Kinetic Computer Code for Reactivity Transient Analysis in
  Nuclear Research Reactors
  AIREKMOD-RR User's Guide.

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

12. PROGRAMMING LANGUAGE(S) USED -
IAEA1274/01: FORTRAN-77

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED - VAX/VMS.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - No
additional informations are required.

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

16. MATERIAL AVAILABLE -
IAEA1274/01:
AIREKMOD.FOR AIREKMOD Source File
AIREKMOD.OUT AIREKMOD Output File
HEU.DAT AIREKMOD Test-Case Data
user's guide             AIREKMOD-RR User's Guide                   WRKPT

17. CATEGORIES -

- G. Radiological Safety, Hazard and Accident Analysis

Keywords: LOSS-OF-COOLANT ACCIDENT, REACTOR KINETICS

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