IAEA1274 AIREKMOD-RR.

AIREKMOD-RR

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.

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.

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.

Less than 20 sec are required for a sample problem related to fast reactivity insertion.

Can be run on Personal Computers (P.C.).

AIREKMOD-RR is a modified version of the AIREK-MOD Code.

• 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).

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

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

VAX/VMS.

No additional informations are required.

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