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NEA-0398 COSTAX-BOIL.

COSTAX-BOIL, Transient Dynamic Analysis of BWR and PWR in Axial Geometry

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1. NAME OR DESIGNATION OF PROGRAM:  COSTAX-BOIL.
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2. COMPUTERS
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Program name Package id Status Status date
COSTAX-BOIL NEA-0398/01 Tested 01-APR-1974

Machines used:

Package ID Orig. computer Test computer
NEA-0398/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

Transient analysis of BWR are performed in the time domain. The code couples the two velocity groups neutron diffusion kinetic calculations (up to 10 delayed neutron groups) in one dimension (axial) with the heat conduction equations in the fuel rods and a two phase flow dynamics calculation for the typical coolant channel. The program is intended for the analysis of intermediate accidents or severe operational transients  in which a detailed spatial representation is essential.
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4. METHOD OF SOLUTION

Doppler and void reactivity feedback are accounted for pointwise. A flexible input allows representation of reactivity transients, flow recirculation, or inlet enthalpy transients, or an arbitrary mixture of them, including control rod bank movement. No pressure variation is possible in the present version.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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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-0398/01 01-APR-1974 Tested at NEADB
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10. REFERENCES

- G. Forti and E. Vincenti:
  'The Codes COSTANZA for the Dynamics of Liquid-Cooled Nuclear
  Reactors'
  EUR 3633 e (1967)
- G. Forti:
  'A Dynamic Model for the Cooling Channels of a Boiling Nuclear
  Reactor with Forced Circulation and High Pressure Level'
  EUR 4052 e (1968)
NEA-0398/01, included references:
- G. Forti:
  COSTAX-BOIL - A Computer Programme of the CONSTANZA Series for the
  Axial Dynamics of BWR and PWR Nuclear Reactors
  EUR 4497 e (1970)
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0398/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  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: G. Forti
J.R.C. EURATOM
Ispra Establishment, Italy.
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16. MATERIAL AVAILABLE
NEA-0398/01
File name File description Records
NEA0398_01.001 SOURCE PROGRAM (FORTRAN) 2747
NEA0398_01.002 SAMPLE PROBLEM 51
NEA0398_01.003 OUTPUT LIST OF SAMPLE PROBLEM 865
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17. CATEGORIES
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • G. Radiological Safety, Hazard and Accident Analysis
  • H. Heat Transfer and Fluid Flow

Keywords: BWR reactors, Doppler coefficient, enthalpy, feedback, heat transfer, hydrodynamics, loss-of-coolant accident, neutron diffusion equation, transients, two-phase flow.