Computer Programs

NEA-0251 PREST.

NEA-0251 PREST.

PREST, Pressure Temperature Transients, I Inhalation in Containment Building from LOCA

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, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: PREST.

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2. COMPUTERS

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Program name	Package id	Status	Status date
PREST	NEA-0251/01	Tested	01-JUN-1969

Machines used:

Package ID	Orig. computer	Test computer
NEA-0251/01	IBM 360 series	IBM 360 series

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3. NATURE OF PHYSICAL PROBLEM SOLVED

The programme is intended for the determination of pressure and temperature transient inside the containment building, following a loss-of-coolant accident due to a rupture in the primary cooling system of a nuclear power plant having water as the primary coolant. The model includes the calculation of the radiation doses incurred to the thyroid due to inhalation of radioactive iodine released outside the containment building.

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4. METHOD OF SOLUTION

The energy equation is solved at each time step by using the Newton method. In order to determine the heat exchange with structures inside the containment building as well as with the outside atmosphere, the structures are treated in slab geometry.
The resulting Fourier equations for heat conduction are solved numerically by using an implicit form to avoid stability problems.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

   max. number of internal slabs - 6
   max. number of external slabs - 4
   max. number of meshes in each slab - 100.

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6. TYPICAL RUNNING TIME: About 10 minutes for a typical 24 hours transient.

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7. UNUSUAL FEATURES OF THE PROGRAM

The mathematical model adopted allows both the blowdown phase of the primary coolant and the subsequent phase of the accident to be studied. The programme may account for the presence of the consequence-limiting engineered safeguards, such as internal and/or external spray systems.
Plots of pressure, temperature, and integrated dose-rate versus time may be obtained by means of the CALCOMP device.

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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-0251/01	01-JUN-1969	Tested at NEADB

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10. REFERENCES

- G. Gaggero, P.M. Gerini, G. Leoni, J.B. Van Erp:
"MACACO-PREST", An Analog Model and a Digital Code for Containment Studies
EUR 3927.E (1968).

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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-0251/01	FORTRAN-IV

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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED: O.S. IBM 360/65.

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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS: The programme needs the CALCOMP subroutine package.

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15. NAME AND ESTABLISHMENT OF AUTHOR

G. Gaggero - CETIS, EURATOM C.C.R., 21020 - Ispra (Varese) Italy
P.M. Gerini - CISE, Segrate (Milano) Italy.
G. Leoni - AGIP Nucleare, San Donato Milanese (Milano) Italy.
J.B. Van Erp- EURATOM C.C.R., 21020 - Ispra (Varese) Italy.

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16. MATERIAL AVAILABLE

NEA-0251/01

File name	File description	Records
NEA0251_01.001	SOURCE & DATA 360/65	1865
NEA0251_01.002	OUTPUT	642

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17. CATEGORIES

G. Radiological Safety, Hazard and Accident Analysis
H. Heat Transfer and Fluid Flow

Keywords: blowdown, containment, doses, heat transfer, loss-of-coolant accident, power plants, pressure, reactor safety, slabs, temperature, transients.