Computer Programs
NEA-0371 CYLFUX.
NEA-0371 CYLFUX.
CYLFUX, Fast Reactor Reactivity Transients Simulation in LWR by 2-D 2 Group Diffusion
NAME OR DESIGNATION OF PROGRAM,
COMPUTER,
NATURE OF PHYSICAL PROBLEM SOLVED,
METHOD OF SOLUTION,
RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM,
TYPICAL RUNNING TIME,
UNUSUAL FEATURES OF THE PROGRAM,
RELATED AND AUXILIARY PROGRAMS,
STATUS,
REFERENCES,
MACHINE REQUIREMENTS,
LANGUAGE,
OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED,
ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS,
NAME AND ESTABLISHMENT OF AUTHOR,
MATERIAL,
CATEGORIES
1. NAME OR DESIGNATION OF PROGRAM: CYLFUX.
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Program name |
Package id |
Status |
Status date |
CYLFUX |
NEA-0371/01 |
Tested |
01-NOV-1973 |
Package ID |
Orig. computer |
Test computer |
NEA-0371/01 |
IBM 370 series |
IBM 370 series |
3. NATURE OF PHYSICAL PROBLEM SOLVED
A 2-dimensional calculation of the 2-group, space-dependent neutron diffusion equations is performed in r-z geometry using an arbitrary number of groups of delayed neutron precursors. The program is designed to simulate fast reactivity excursions in light water reactors taking into account Doppler feedback via adiabatic heatup of fuel. Axial motions of control rods may be considered including scram action on option.
4. METHOD OF SOLUTION
The differential equations are solved at each time step by an explicit finite difference method using two time levels. The stationary distributions are obtained by using the same algorithm.
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
No restriction to the number of space points and delayed neutron energy groups besides the computer size.
6. TYPICAL RUNNING TIME
Running time depends upon problem size, increasing almost linearly with the number of space points.
Running time is about 0.0001 sec on IBM 360/91 for one space point during one time step.
7. UNUSUAL FEATURES OF THE PROGRAM: Transients may be calculated by several successive steps.
8. RELATED AND AUXILIARY PROGRAMS
A program is also available for r-, x-, z-, x-y- and x-y-z geometries.
Package ID |
Status date |
Status |
NEA-0371/01 |
01-NOV-1973 |
Tested at NEADB |
10. REFERENCES
- A.Schmidt:
PIMFUX, Ein 3-Dimensionales Rechenmodell zur Simulation von
Reaktivitaetsstoerfaellen nach der Zweigruppen-Diffusionstheorie
MRR 88 (August 1971).
11. MACHINE REQUIREMENTS
Depends on problem size, e.g. 480k memory for about 10,000 space points and 6 groups of delayed neutron precursors.
12. PROGRAMMING LANGUAGE(S) USED
Package ID |
Computer language |
NEA-0371/01 |
FORTRAN-IV |
13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED: PBS16 for SIEMENS. OS release 21 for IBM.
14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
Subroutine MEMORY defines size of work area for all necessary arrays which has to be stated according to the computer size.
15. NAME AND ESTABLISHMENT OF AUTHOR
A. Schmidt
Laboratorium fuer Reaktorregelung und Anlagensicherung
Technische Universitaet Muenchen
D-8046 Garching
Fed. Rep. Germany.
NEA-0371/01
File name |
File description |
Records |
NEA0371_01.001 |
SOURCE PROGRAM (FORTRAN) |
5047 |
NEA0371_01.002 |
JCL+OVERLAY CARDS+SAMPLE INPUT |
96 |
NEA0371_01.003 |
OUTPUT LIST OF SAMPLE PROBLEM |
2126 |
- F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
Keywords: Doppler coefficient, LWR reactors, delayed neutrons, excursions, finite difference method, kinetics, neutron diffusion equation, r-z, space dependence, space-time, two-dimensional, two-group.