last modified: 01-NOV-1973 | catalog | categories | new | search |

NEA-0371 CYLFUX.

CYLFUX, Fast Reactor Reactivity Transients Simulation in LWR by 2-D 2 Group Diffusion

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1. NAME OR DESIGNATION OF PROGRAM:  CYLFUX.
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2. COMPUTERS
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Program name Package id Status Status date
CYLFUX NEA-0371/01 Tested 01-NOV-1973

Machines used:

Package ID Orig. computer Test computer
NEA-0371/01 IBM 370 series IBM 370 series
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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.
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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.
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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.
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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.
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7. UNUSUAL FEATURES OF THE PROGRAM:  Transients may be calculated by several successive steps.
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8. RELATED AND AUXILIARY PROGRAMS

A program is also available for r-, x-, z-, x-y- and x-y-z geometries.
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9. STATUS
Package ID Status date Status
NEA-0371/01 01-NOV-1973 Tested at NEADB
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10. REFERENCES

- A.Schmidt:
  PIMFUX, Ein 3-Dimensionales Rechenmodell zur Simulation von
  Reaktivitaetsstoerfaellen nach der Zweigruppen-Diffusionstheorie
  MRR 88 (August 1971).
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11. MACHINE REQUIREMENTS

Depends on problem size, e.g. 480k memory for  about 10,000 space points and 6 groups of delayed neutron precursors.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0371/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  PBS16 for SIEMENS. OS release 21 for IBM.
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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.
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15. NAME AND ESTABLISHMENT OF AUTHOR

A. Schmidt
Laboratorium fuer Reaktorregelung und Anlagensicherung
Technische Universitaet Muenchen
D-8046 Garching
Fed. Rep. Germany.
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16. MATERIAL AVAILABLE
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
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17. CATEGORIES
  • 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.