1. NAME AND TITLE
AIREKMODRR: Reactivity Transients in Nuclear Research Reactors.
2. CONTRIBUTOR
Centre
de Radioprotection et Surete (C.R.S.), B.P. 1017 Alger Gare, Alger 16000,
Algeria and
Centre de developpement des Systemes Energetiques (C.D.S.E.), B.P. 180
AinOussara, 17200, Djelfa, Algeria through the OECD Nuclear Energy Agency Data
Bank, IssylesMoulineaux, France.
3. CODING LANGUAGE AND COMPUTER
Fortran 77; DEC VAX Series (P00588D0VAX00).
4. NATURE OF PROBLEM SOLVED
AIREMODRR 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 onedimensional heat balance equation. The calculations are restricted to a single equivalent unit cell which consists of fuel, clad and coolant.
5. 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.
6. RESTRICTIONS OR LIMITATIONS
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..
7. TYPICAL RUNNING TIME
Less than 20 sec are required for a sample problem related to fast reactivity insertion.
8. COMPUTER HARDWARE REQUIREMENTS
VAX/VMS.
9. COMPUTER SOFTWARE REQUIREMENTS
A FORTRAN compiler is required. No executables are included with the package.
10. REFERENCES
a) Included Documentation:
A Point Kinetic Computer Code for Reactivity Transient Analysis in Nuclear Research Reactors AIREKMODRR User's Guide.
11. CONTENTS OF CODE PACKAGE
The package is distributed on a CD which includes source code, sample input and output files along with the documentation listed in 10a.
12. DATE OF ABSTRACT
June 2013.
KEYWORDS: LOSSOFCOOLANT ACCIDENT, REACTOR KINETICS