last modified: 01-SEP-1976 | catalog | categories | new | search |

NEA-0457 DRUGEVO.

DRUGEVO, Time-Dependent Containment Pressure and Temperature in BWR or PWR LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  DRUGEVO.
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2. COMPUTERS
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Program name Package id Status Status date
DRUGEVO NEA-0457/01 Tested 01-SEP-1976

Machines used:

Package ID Orig. computer Test computer
NEA-0457/01 IBM 370 series IBM 370 series
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3. NATURE OF PHYSICAL PROBLEM SOLVED

DRUGEVO calculates the time dependent course of pressures and temperatures in the different compartments of the containment of a BWR or PWR in the case of a loss of coolant accident.
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4. METHOD OF SOLUTION

Numerical integration of ordinary first order differential equations by extrapolation methods.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

A maximum of:
   30 compartments
   60 connections between the compartments (opened or closed with rupture disks)
    5 horizontal flaps
   10 points for time dependent input parameters, except the factor of carry-over of water (8 points).
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6. TYPICAL RUNNING TIME

For a system of 4 compartments, 4 connections  and no flaps, for a problem time of 1 second, about 4 minutes of running time are required.
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7. UNUSUAL FEATURES OF THE PROGRAM

The program simulates the possible  change from the state of saturation to superheating and vice versa in each compartment. Release of coolant and heat sources can be considered in all compartments simultaneously.
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8. RELATED AND AUXILIARY PROGRAMS

Rates of steam and/or water calculated with the program DAWAQ (tape) may be additional input.
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9. STATUS
Package ID Status date Status
NEA-0457/01 01-SEP-1976 Tested at NEADB
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10. REFERENCES

- International Formulation Committee (IFC):
  'A Formulation of the Thermodynamic Properties of Ordinary Water Substance'
  (1967).
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11. MACHINE REQUIREMENTS

110 kbytes of core storage. Optionally 2 tapes (additional input and plot tape).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0457/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 370/DOS.
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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

   W. Muehlbauer and H. Stepan

   TUV Bayern E.V.
   Eichstaetterstr. 5
   D-8000 Munich 21
   Germany, F.R.
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16. MATERIAL AVAILABLE
NEA-0457/01
File name File description Records
NEA0457_01.001 SOURCE PROGRAM (F4) EBCDIC 2053
NEA0457_01.002 SAMPLE PROBLEM INPUT DATA 24
NEA0457_01.003 SAMPLE PROBLEM PRINTED OUTPUT 415
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: BWR reactors, loss-of-coolant accident, pressure, pwr reactors, reactor safety, temperature, thermodynamics, time dependence.