last modified: 01-JAN-1977 | catalog | categories | new | search |

NEA-0533 COSTAX-BWR.

COSTAX-BWR, Coupled Time-Dependent 2 Group Neutron Diffusion and 2 Phase Fuel Rod Coolant Flow

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1. NAME OR DESIGNATION OF PROGRAM:  COSTAX-BWR.
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2. COMPUTERS
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Program name Package id Status Status date
COSTAX-BWR NEA-0533/01 Tested 01-JAN-1977

Machines used:

Package ID Orig. computer Test computer
NEA-0533/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

Time dependent two group neutron  diffusion equations coupled with two phase flow coolant channel model and heat diffusion in fuel rods - solves also the complete steady state problem with feedbacks.
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4. METHOD OF SOLUTION

Backwards finite differences in space and time - direct simultaneous solution for neutron diffusion equations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

BWR transients including pressure variation but excluding very fast depressurization (dynamic wave propagation is not considered).
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6. TYPICAL RUNNING TIME:  Less than 2 minutes for a typical transient on IBM 370.
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7. UNUSUAL FEATURES OF THE PROGRAM

Pointwise feedback on all nuclear constants - subcooled boiling model with special formulation. Zuber  -Findlay's model for vapour slip. Complete steady state solution using time dependent equations to avoid any discontinuity between steady state and transient calculations.
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8. RELATED AND AUXILIARY PROGRAMS

FRANCESCA-BWR - The Coolant Channel  Code COSTAX-BOIL - A First Version with Less Capability and Specialization.
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9. STATUS
Package ID Status date Status
NEA-0533/01 01-JAN-1977 Tested at NEADB
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10. REFERENCES
NEA-0533/01, included references:
- G.Forti:
  'COSTAX-BWR A Numerical Programme for the Axial Dynamics of BWR
  Nuclear Reactors.'
  EUR 4837.E.
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11. MACHINE REQUIREMENTS:  140k bytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0533/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 370 O.S.
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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

      G. Forti
      Joint Research Centre
      21020 - Ispra Italy
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16. MATERIAL AVAILABLE
NEA-0533/01
File name File description Records
NEA0533_01.002 PROGRAM SOURCE - FORTRAN IV 2760
NEA0533_01.003 SAMPLE PROBLEM DATA 46
NEA0533_01.004 SAMPLE PROBLEM OUTPUT 1591
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, feedback, fuel rods, neutron diffusion equation, steady-state conditions, time dependence, two-group, two-phase flow.