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NEA-0533 COSTAX-BWR.

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

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, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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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.