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NEA-0401 ZOCO-VI.

ZOCO-6, Temperature Transients in BWR and PWR Containment During LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  ZOCO-VI.
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2. COMPUTERS
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Program name Package id Status Status date
ZOCO-6 NEA-0401/01 Tested 01-DEC-1978

Machines used:

Package ID Orig. computer Test computer
NEA-0401/01 IBM 360 series IBM 360 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

ZOCO-VI is a multi-node computer  code which calculates the time and space dependent pressure distribution in containments of water-cooled nuclear power reactors  following a loss-of-coolant accident. It should be used primarily for the short term behaviour but can also be used for the long term  behaviour.
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4. METHOD OF SOLUTION

Using the equations of the mass balances for steam, water and air, and the energy and volume balances, for each pressure node, four or six (nonthermodynamic equilibrium) ordinary non-linear differential equations for the time dependent variations  of the temperature and the masses of steam, water and air are obtained. The solution of the system of differential equations will  be performed using the integration and iteration procedure DIFSYS.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The quantity of the pressure nodes is only limited by the computer capacity and the computing time.
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6. TYPICAL RUNNING TIME

The running time depends on the complexity of  the  problem and on the quantity of pressure nodes.
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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-0401/01 01-DEC-1978 Tested at NEADB
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10. REFERENCES

- G. Mansfeld:
  'ZOCO VI' - A Computer Code for the Calculation of Pressure
   Distributions in Time and  Space for Pressurised Water Reactors
   Programme Description.
  Laboratorium fuer Reaktorregelung und Anlagensicherung Garsching
  Technische Universitat Munich
  MRR-P-14 (December 1974), (in German).
- D. Brosche:
  'ZOCO-V, Ein Rechenmodell zur Berechnung von zeitlichen und
   oertlichen Druckverteilungen in Reaktorsicherheitsbehaeltern
  Laboratorium fuer Reaktorregelung und Anlagensicherung
  Technische Universitaet Muenchen
  MRR 104 (April 1972), (in German).
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11. MACHINE REQUIREMENTS:   Usually 240k memory is required.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0401/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  Siemens PBS 4004 version 17, IBM 360/OS.
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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

D. Brosche
Laboratorium fuer Reaktorregelung und
Anlagensicherung
Technische Universitaet
Munich, Germany
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16. MATERIAL AVAILABLE
NEA-0401/01
File name File description Records
NEA0401_01.001 SOURCE PROGRAM (F4,EBCDIC) 3635
NEA0401_01.002 DUMMY ROUTINE 'DATE' AND 'ITIME' 8
NEA0401_01.003 SAMPLE PROBLEM INPUT DATA 111
NEA0401_01.004 SAMPLE PROBLEM PRINTED OUTPUT 6274
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: loss-of-coolant accident, pressure, temperature, transients, water cooled reactors.