1. NAME AND TITLE
PREST: Calculator of Pressure and Temperature Transient in Containment Studies.
2. CONTRIBUTOR
European Atomic Energy Community, EURATOM, through the OECD NEA Data Bank, Gif-sur-Yvette, France.
3. CODING LANGUAGE AND COMPUTER
Fortran IV; IBM 360-370.
4. NATURE OF PROBLEM SOLVED
PREST determines transient pressure and temperature 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.
The mathematical model adopted allows both the blowdown phase of the primary coolant and the
subsequent phase of the accident to be studied. The program may account for the presence of the
consequence-limiting engineered safeguards, such as internal and/or external Spray Systems.
5. 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. Plots of
pressure, temperature, and integrated dose-rate versus time may be obtained by means of the Calcomp
Device.
6. RESTRICTIONS OR LIMITATIONS
Maximum number of internal slabs 6
Maximum number of external slabs 4
Maximum number of meshes in each slab 100
7. TYPICAL RUNNING TIME
PREST requires about 10 minutes of running time for a typical 24-hour transient.
8. COMPUTER HARDWARE REQUIREMENTS
PREST is operable on the IBM 360/370 computers.
9. COMPUTER SOFTWARE REQUIREMENTS
A Fortran IV compiler is required. The code is executed under the IBM 360/65 operating system.
10. REFERENCE
G. Gaggero, P. M. Gerini, G. Leoni, and J. B. van Erp, "MACACO-PREST, An Analog Model
and a Digital Code for Containment Studies," EUR 3927.e (1968).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
codes and sample problem input and output.
12. DATE OF ABSTRACT
January 1982.
KEYWORDS: SLAB; GAUSSIAN PLUME MODEL; LWR; REACTOR ACCIDENT; ENVIRONMENTAL DOSE