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NEA-0853 NAUA-MOD5.

NAUA-MOD5 NAUA-MOD5/M, Aerosols in Reactor Containment During Meltdown

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1. NAME OR DESIGNATION OF PROGRAM:  NAUA-MOD5, NAUA-MOD5/M.
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2. COMPUTERS
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Program name Package id Status Status date
NAUA-MOD5 NEA-0853/02 Tested 08-NOV-1988
NAUA-MOD5 NEA-0853/03 Tested 08-NOV-1988

Machines used:

Package ID Orig. computer Test computer
NEA-0853/02 IBM 3090 IBM 3090
NEA-0853/03 IBM 3090 DEC VAX 8810
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3. DESCRIPTION OF PROGRAM OR FUNCTION

NAUA-MOD5 and NAUA-MOD5/M calculate the behaviour of a polydisperse aerosol system in a closed container. This container can be subdivided into a number of subcompartments geometrically separated but coupled by gas flows. For NAUA-MOD5/M an arbitrary configuration of subcompartments and flow patterns can be treated.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
NEA-0853/02
The tests included in this package were run by NEA-DB on an IBM 3090 computer. The total execution time for all the test cases for NAUA-MOD5 was about 48 CPU minutes. The test case for NAUA-MOD5/M required 24 minutes of CPU time.

NEA-0853/03
The tests included in this package were run by NEA-DB on a VAX 8810 computer. The total execution time for all the test cases for NAUA-MOD5 was about 6 hours and 30 minutes. The test case  for NAUA-MOD5/M required 36 minutes of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-0853/02 08-NOV-1988 Tested at NEADB
NEA-0853/03 08-NOV-1988 Tested at NEADB
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10. REFERENCES:
NEA-0853/02, included references:
- H. Bunz, W. Schikarski and W. Schoeck:
  The Role of Aerosol Behavior in Light Water Reactor Core Melt
  Accidents. (Nuclear Technology, Vol. 53, pp. 141-146, May 1981)
- W. Schoeck, H. Bunz and M. Koyro:
  Measurement of Steam Condensation on Aerosols under LWR
  Accident Conditions
  KfK-3153  (August 1981)
- H. Bunz, M. Koyro and W. Schoeck:
  NAUA-MOD3 - A Computer Code for the Description of the Aerosol
  Behaviour in a Condensing Athmosphere
  KfK-3154  (September 1981)
- H. Bunz, M. Koyro and W. Schoeck:
  NAUA-MOD4 - A Code for Calculating Aerosol Behaviour in LWR
  Core Melt Accidents, Code Description and Users Manual
  KfK-3554  (August 1983)
- H. Bunz, M. Koyro and W. Schoeck:
  NAUA-MOD5 and NAUA-MOD5-M - Two Computer Codes for the Description
  of the Aerosol Behaviour in the Containment System of a LWR after
  a Core Melt Accident
  KfK-4278  (September 1987)
NEA-0853/03, included references:
- H. Bunz, W. Schikarski and W. Schoeck:
  The Role of Aerosol Behavior in Light Water Reactor Core Melt
  Accidents. (Nuclear Technology, Vol. 53, pp. 141-146, May 1981)
- W. Schoeck, H. Bunz and M. Koyro:
  Measurement of Steam Condensation on Aerosols under LWR
  Accident Conditions
  KfK-3153  (August 1981)
- H. Bunz, M. Koyro and W. Schoeck:
  NAUA-MOD3 - A Computer Code for the Description of the Aerosol
  Behaviour in a Condensing Athmosphere
  KfK-3154  (September 1981)
- H. Bunz, M. Koyro and W. Schoeck:
  NAUA-MOD4 - A Code for Calculating Aerosol Behaviour in LWR
  Core Melt Accidents, Code Description and Users Manual
  KfK-3554  (August 1983)
- H. Bunz, M. Koyro and W. Schoeck:
  NAUA-MOD5 and NAUA-MOD5-M - Two Computer Codes for the Description
  of the Aerosol Behaviour in the Containment System of a LWR after
  a Core Melt Accident
  KfK-4278  (September 1987)
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11. MACHINE REQUIREMENTS:
NEA-0853/02
All test cases ran on an IBM 3090 in 656K bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0853/02 FORTRAN-77
NEA-0853/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-0853/02
MVS/XA (IBM 3090).

NEA-0853/03
VAX/VMS V4.6 and V5.0-1.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Laboratorium fur Aerosolphysik und Filtertechnik
Projekt Nukleare Sicherheit
Kernforschungszentrum Karlsruhe GmbH
KARLSRUHE
Germany
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16. MATERIAL AVAILABLE
NEA-0853/02
File name File description Records
NEA0853_02.001 INFO FILE 137
NEA0853_02.002 NAUA MOD5 FORTRAN-77 SOURCE 1950
NEA0853_02.003 NAUA MOD5-M FORTRAN-77 SOURCE 1121
NEA0853_02.004 CBRT FORTRAN-77 PACKAGE 1426
NEA0853_02.005 JCL USED IN TESTING 279
NEA0853_02.006 ORIGINAL JCL 100
NEA0853_02.007 INPUT FOR T/CASE 1 112
NEA0853_02.008 INPUT FOR T/CASE 2 113
NEA0853_02.009 INPUT FOR T/CASE 3 FIRST STEP 71
NEA0853_02.010 INPUT FOR T/CASE 3 SECOND STEP 42
NEA0853_02.011 INPUT FOR T/CASE 4 15
NEA0853_02.012 THERMODYNAMIC EBCDIC I/P T/CASE 4 3913
NEA0853_02.013 FT06 O/P T/CASE 1 5540
NEA0853_02.014 FT06 O/P T/CASE 2 5532
NEA0853_02.015 FT06 O/P T/CASE 3 12725
NEA0853_02.016 FT06 O/P T/CASE 4 4188
NEA-0853/03
File name File description Records
NEA0853_03.001 INFO FILE 150
NEA0853_03.002 NAUA MOD5 FORTRAN-77 SOURCE 1950
NEA0853_03.003 NAUA MOD5-M FORTRAN-77 SOURCE 1121
NEA0853_03.004 FORTRAN ZEIT,JTIME,CPUREL SOURCE 14
NEA0853_03.005 CBRT FORTRAN-77 PACKAGE 1426
NEA0853_03.006 COMMAND PROCEDURES 91
NEA0853_03.007 FORTRAN CONVERSION TO BINARY SOURCE 29
NEA0853_03.008 INPUT FOR T/CASE 1 112
NEA0853_03.009 INPUT FOR T/CASE 2 113
NEA0853_03.010 INPUT FOR T/CASE 3 FIRST STEP 71
NEA0853_03.011 INPUT FOR T/CASE 3 SECOND STEP 42
NEA0853_03.012 INPUT FOR T/CASE 4 15
NEA0853_03.013 THERMODYNAMIC ASCII I/P T/CASE 4 3913
NEA0853_03.014 FOR006 O/P T/CASE 1 5565
NEA0853_03.015 FOR006 O/P T/CASE 2 5558
NEA0853_03.016 FOR006 O/P T/CASE 3 12727
NEA0853_03.017 FOR006 O/P T/CASE 4 4189
NEA0853_03.018 ORIGINAL IBM OUTPUT (SHORTENED) 1721
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: LWR reactors, accidents, aerosols, containment, meltdown, reactor safety.