NEA-0160 COSTANZA-AX.
COSTANZA-AX, 1-D Neutronics and Thermodynamics of Liquid Cooled Reactor in Axial Geometry
COSTANZA-CYL, 1-D Neutronics and Thermodynamics of Liquid Cooled Reactor in Cylindrical Geometry
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, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| COSTANZA-AX | NEA-0160/01 | Tested | 01-DEC-1968 |
| COSTANZA-CYL | NEA-0160/02 | Tested | 01-NOV-1967 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0160/01 | IBM 360 series | IBM 360 series |
| NEA-0160/02 | IBM 360 series | IBM 360 series |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
Purpose of the programmes is to study reactor dynamics, considering the variation of the spatial flux distribution. The two programmes COSTANZA-CYL and COSTANZA-AX, solve the kinetics diffusion equations in two groups and one dimension (plane geometry for COSTANZA-AX, radial geometry for COSTANZA-CYL). The neutronic calculation is coupled with the calculation of the heat transmission from the fuel to the cladding and to the coolant, and with the thermo-hydraulics of channels with forced circulation of liquid coolant. The geometry of fuel element and channel may be cylindrical or slab. Up to ten groups of delayed neutrons are allowed. Temperature feedback of fuel (Doppler) and coolant are considered independently and affect the nuclear constants. Control rod movement or diffused poison concentrations are simulated by externally imposed variations of the thermal absorption cross section in the different regions of the reactors. Inlet temperatures and mass flow in the coolant channels may be varied according to any externally given time table.
Purpose of the programmes is to study reactor dynamics, considering the variation of the spatial flux distribution. The two programmes COSTANZA-CYL and COSTANZA-AX, solve the kinetics diffusion equations in two groups and one dimension (plane geometry for COSTANZA-AX, radial geometry for COSTANZA-CYL). The neutronic calculation is coupled with the calculation of the heat transmission from the fuel to the cladding and to the coolant, and with the thermo-hydraulics of channels with forced circulation of liquid coolant. The geometry of fuel element and channel may be cylindrical or slab. Up to ten groups of delayed neutrons are allowed. Temperature feedback of fuel (Doppler) and coolant are considered independently and affect the nuclear constants. Control rod movement or diffused poison concentrations are simulated by externally imposed variations of the thermal absorption cross section in the different regions of the reactors. Inlet temperatures and mass flow in the coolant channels may be varied according to any externally given time table.
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7. UNUSUAL FEATURES OF THE PROGRAM
The thermal resistance of the gap between fuel and clad and the heat transfer coefficient at every axial level of the channel are variable functions of thermodynamics parameters. In the initialization of each problem criticality may be searched for by varying poison insertion in any wanted zone. A free test routine may be used to insert new specifications when any wanted conditions are reached during the transients.
The thermal resistance of the gap between fuel and clad and the heat transfer coefficient at every axial level of the channel are variable functions of thermodynamics parameters. In the initialization of each problem criticality may be searched for by varying poison insertion in any wanted zone. A free test routine may be used to insert new specifications when any wanted conditions are reached during the transients.
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| Package ID | Status date | Status |
|---|---|---|
| NEA-0160/01 | 01-DEC-1968 | Tested at NEADB |
| NEA-0160/02 | 01-NOV-1967 | Tested at NEADB |
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10. REFERENCES
- A. Agazzi, G. Forti, E. Vincenzi:
COSTANZA CYLINDRICAL A Cylindrical One-Dimensional Dynamics Code for Liquid-Cooled Multi-Channel Nuclear Reactors
EUR. 3171E (1966).
- A. Agazzi, G. Forti, E. Vincenzi:
COSTANZA CYLINDRICAL A Cylindrical One-Dimensional Dynamics Code for Liquid-Cooled Multi-Channel Nuclear Reactors
EUR. 3171E (1966).
NEA-0160/01, included references:
- G. Forti and E. Vincenti:The codes COSTANZA for the Dynamics of Liquid-Cooled Nuclear
Reactors. EUR 3633e (1967)
NEA-0160/02, included references:
- G. Forti and E. Vincenti:The Codes COSTANZA for the Dynamics of Liquid-Cooled Nuclear
Reactors. EUR 3633e (1967)
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| Package ID | Computer language |
|---|---|
| NEA-0160/01 | FORTRAN-IV |
| NEA-0160/02 | FORTRAN-IV |
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NEA-0160/01
| File name | File description | Records |
|---|---|---|
| NEA0160_01.001 | SOURCE & DATA 360/65 | 1352 |
| NEA0160_01.002 | OUTPUT | 755 |
NEA-0160/02
| File name | File description | Records |
|---|---|---|
| NEA0160_02.001 | Information file | 32 |
| NEA0160_02.002 | COSTANZA-CYL source (FORTRAN) + input data | 1281 |
| NEA0160_02.003 | COSTANZA-CYL printed output | 535 |
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- F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
Keywords: Doppler coefficient, absorption, cladding, control elements, coolants, cross sections, cylinders, delayed neutrons, diffusion, finite difference method, fuel elements, heat transfer, liquid cooled reactors, one-dimensional, poisoning, reactor kinetics, slabs, temperature feedback, thermodynamics, two-group.