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NEA-0393 CARNAC.

CARNAC, Neutron Flux and Neutron Spectra in Criticality Accident

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1. NAME OR DESIGNATION OF PROGRAM:  CARNAC.
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2. COMPUTERS
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Program name Package id Status Status date
CARNAC NEA-0393/01 Tested 01-OCT-1976

Machines used:

Package ID Orig. computer Test computer
NEA-0393/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

Calculation of flux and neutron spectra in the case of a criticality accident.
The method is unsophisticated but fast. The program is divided into  two parts

(1) The code CRITIC is based on the Fermi age equation and evaluates  the neutron number per fission emitted from a moderate critical system and its energy spectrum.
(2) The code NARCISSE uses concrete current albedo, evaluates the  product of neutron reflection on walls of the source containment and calculates the resulting flux at any point, and its energy distribution into 21 groups. The results obtained seem satisfactory, if compared with a Monte Carlo program.
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4. METHODS: METHOD OF SOLUTION
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME

Times are for an IBM 360/91

CRITIC calculation - less than 30 seconds.
NARCISSE calculation - 3 minutes for flux evaluation at one point chosen inside the containment.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0393/01 01-OCT-1976 Tested at NEADB
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10. REFERENCES
NEA-0393/01, included references:
- J.Bessis:
  Calcul rapide du flux et du spectre neutroniques en cas d'accident
  de criticite (programme CARNAC)
  CEA-N-1612 (May 1973).
- J.Bessis and M. de Mareuil:
  Notice D'exploitation du Programme de Calcul CARNAC
  NOTE S.E.S.R. No. 5 (14 Mars 1973).
- J. Bessis:
Note CEA-N-1612 translated into English ORNL-tr-2825
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0393/01 FORTRAN-IV
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13. SOFTWARE REQUIREMENTS: OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

   J.Bessis
   Departement de Surete Nucleaire
   Commissariat a l'Energie Atomique.
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16. MATERIAL AVAILABLE
NEA-0393/01
File name File description Records
NEA0393_01.001 SOURCE PROGRAM (F4) EBCDIC 746
NEA0393_01.002 SAMPLE PROBLEM INPUT DATA 127
NEA0393_01.003 SAMPLE PROBLEM PRINTED OUTPUT 1460
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: accidents, albedo, criticality, neutron flux, neutron spectra, reactor safety.